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Sample records for utilizing phosphorus-31 nuclear

  1. A sex-specific metabolite identified in a marine invertebrate utilizing phosphorus-31 nuclear magnetic resonance.

    Directory of Open Access Journals (Sweden)

    Robert A Kleps

    Full Text Available Hormone level differences are generally accepted as the primary cause for sexual dimorphism in animal and human development. Levels of low molecular weight metabolites also differ between men and women in circulating amino acids, lipids and carbohydrates and within brain tissue. While investigating the metabolism of blue crab tissues using Phosphorus-31 Nuclear Magnetic Resonance, we discovered that only the male blue crab (Callinectes sapidus contained a phosphorus compound with a chemical shift well separated from the expected phosphate compounds. Spectra obtained from male gills were readily differentiated from female gill spectra. Analysis from six years of data from male and female crabs documented that the sex-specificity of this metabolite was normal for this species. Microscopic analysis of male and female gills found no differences in their gill anatomy or the presence of parasites or bacteria that might produce this phosphorus compound. Analysis of a rare gynandromorph blue crab (laterally, half male and half female proved that this sex-specificity was an intrinsic biochemical process and was not caused by any variations in the diet or habitat of male versus female crabs. The existence of a sex-specific metabolite is a previously unrecognized, but potentially significant biochemical phenomenon. An entire enzyme system has been synthesized and activated only in one sex. Unless blue crabs are a unique species, sex-specific metabolites are likely to be present in other animals. Would the presence or absence of a sex-specific metabolite affect an animal's development, anatomy and biochemistry?

  2. Phosphorus-31 nuclear magnetic resonance spectroscopic study of the canine pancreas: applications to acute alcoholic pancreatitis

    International Nuclear Information System (INIS)

    Janes, N.; Clemens, J.A.; Glickson, J.D.; Cameron, J.L.

    1988-01-01

    The first nuclear magnetic resonance spectroscopic study of the canine pancreas is described. Both in-vivo, ex-vivo protocols and NMR observables are discussed. The stability of the ex-vivo preparation based on the NMR observables is established for at least four hours. The spectra obtained from the in-vivo and ex-vivo preparations exhibited similar metabolite ratios, further validating the model. Metabolite levels were unchanged by a 50% increase in perfusion rate. Only trace amounts of phosphocreatine were observed either in the intact gland or in extracts. Acute alcoholic pancreatitis was mimicked by free fatty acid infusion. Injury resulted in hyperamylasemia, edema (weight gain), increased hematocrit and perfusion pressure, and depressed levels of high energy phosphates

  3. Monitoring of the insecticide trichlorfon by phosphorus-31 nuclear magnetic resonance (31P NMR) spectroscopy

    International Nuclear Information System (INIS)

    Talebpour, Zahra; Ghassempour, Alireza; Zendehzaban, Mehdi; Bijanzadeh, Hamid Reza; Mirjalili, Mohammad Hossein

    2006-01-01

    Trichlorfon is an organophosphorus insecticide, which is extensively being used for protection of fruit crops. Trichlorfon is a thermal labile compound, which cannot be easily determined by gas chromatography (GC) and has no suitable group for sensitive detection by high performance liquid chromatography (HPLC). In this study, a 31 P nuclear magnetic resonance ( 31 P NMR) has been described for monitoring of trichlorfon without any separation step. The quantitative works of 31 P NMR spectroscopy has been performed in the presence of an internal standard (hexamethylphosphoramide). Limit of detection (LOD) for this method has been found to be 55 mg L -1 , without any sample preparation, and the linear working range was 150-5500 mg L -1 . Relative standard deviation (R.S.D.%) of the method for three replicates within and between days was obtained ≤9%. The average recovery efficiency was approximately 99-112%. This method was applied for monitoring trichlorfon in a commercial insecticide sample and tomato sample

  4. Phosphorus-31 NMR (nuclear magnetic resonance) analysis of gold plating baths

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.E.

    1990-01-01

    This report describes the nuclear magnetic resonance (NMR) analysis of the gold plating baths in the Micro-Miniature Electronic Assembly department of Allied-Signal Inc., Kansas City Division (KCD). The baths were analyzed for phosphorylated components. In freshly prepared gold plating baths, a 50-percent aqueous solution of aminotrimethylphosphonate (ATMP) is the principal compound observed. As the bath is used in production, the ATMP breaks down and new materials (phosphate, ADMP, and AMMP) are identified. The NMR method was used to monitor the concentrations of the ATMP and breakdown products for a nine-month period. The 225-liter bath had plated approximately 100 square feet of gold during the nine-month period. These results can be used to predict the performance of baths as they are used in production. The accuracy of the analysis is 96 percent for ATMP and 92 percent for phosphate. The precision (relative standard deviation) is 5.2 percent for ATMP and 4.5 percent for phosphate. 1 ref., 5 figs., 2 tabs.

  5. Phosphorus-31 nuclear magnetic resonance studies of wild-type and glycolytic pathway mutants of Saccharomyces cerevisiae.

    Science.gov (United States)

    Navon, G; Shulman, R G; Yamane, T; Eccleshall, T R; Lam, K B; Baronofsky, J J; Marmur, J

    1979-10-16

    High-resolution phosphorus-31 nuclear magnetic resonance (31P NMR) spectra of wild-type and mutant strains of Saccharomyces cerevisiae were observed at a frequency of 145.7 MHz. Levels of various phosphorus metabolites were investigated upon addition of glucose under both aerobic and anaerobic conditions. Three mutant strains were isolated and their biochemical defects characterized: pfk lacked phosphofructokinase activity; pgi lacked phosphoglucose isomerase activity; and cif had no glucose catabolite repression of the fructose bisphosphatase activity. Each mutant strain was found to accumulate characteristic sugar phosphates when glucose was added to the cell suspension. In the case of the phosphofructokinase deficient mutant, the appearance of a pentose shunt metabolite was observed. 31P NMR peak assignments were made by a pH titration of the acid extract of the cells. Separate signals for terminal, penultimate, and central phosphorus atoms in intracellular polyphosphates allowed the estimation of their average molecular weight. Signals for glycero(3)phosphochline, glycero(3)phosphoserine, and glycero(3) phosphoethanolamine as well as three types of nucleotide diphosphate sugars could be observed. The intracellular pH in resting and anaerobic cells was in the range 6.5--6.8 and the level of adenosine 5'-triphosphate (ATP) low. Upon introduction of oxygen, the ATP level increased considerably and the intracellular pH reached a value of pH 7.2--7.3, irrespective of the external medium pH, indicating active proton transport in these cells. A new peak representing the inorganic phosphate of one of the cellular organelles, whose pH differed from the cytoplasmic pH, could be detected under appropriate conditions.

  6. Deuterium and phosphorus-31 nuclear magnetic resonance study of the interaction of melittin with dimyristoylphosphatidylcholine bilayers and the effects of contaminating phospholipase A2

    International Nuclear Information System (INIS)

    Dempsey, C.E.; Watts, A.

    1987-01-01

    The interaction of bee venom melittin with dimyristoylphosphatidylcholine (DMPC) selectively deuteriated in the choline head group has been studied by deuterium and phosphorus-31 nuclear magnetic resonance (NMR) spectroscopy. The action of residual phospholipase A 2 in melittin samples resulted in mixtures of DMPC and its hydrolytic products that underwent reversible transitions at temperatures between 30 and 35 0 C from extended bilayers to micellar particles which gave narrow single-line deuterium and phosphorus-31 NMR spectra. Similar transitions were observed in DMPC-myristoyllysophosphatidylcholine (lysoPC)-myristic acid mixtures containing melittin but not in melittin-free mixtures, indicating that melittin is able to stabilize extended bilayers containing DMPC and its hydrolytic products in the liquid-crystalline phase. Melittin, free of phospholipase A 2 activity, and at 3-5 mol % relative to DMPC, induced reversible transitions between extended bilayers and micellar particles on passing through the liquid-crystalline to gel phase transition temperature of the lipid, effects similar to those observed in melittin-acyl chain deuteriated dipalmitoylphosphatidylcholine (DPPC) mixtures. LysoPC at concentrations of 20 mol % or greater relative to DMPC induced transitions between extended bilayers and micellar particles with characteristics similar to those induced by melittin. It is proposed that these melittin- and lysoPC-induced transitions share similar mechanisms. The effects of melittin on the quadrupole splittings and T 1 relaxation times of head-group-deuteriated DMPC in the liquid-crystalline phase share features similar to the effects of metal ions on DPPC head groups, indicating that the conformational properties of the choline head group in PC bilayers may be affected by melittin and by metal ions in a similar manner

  7. Deuterium and phosphorus-31 nuclear magnetic resonance study of the interaction of melittin with dimyristoylphosphatidylcholine bilayers and the effects of contaminating phospholipase A/sub 2/

    Energy Technology Data Exchange (ETDEWEB)

    Dempsey, C.E.; Watts, A.

    1987-09-08

    The interaction of bee venom melittin with dimyristoylphosphatidylcholine (DMPC) selectively deuteriated in the choline head group has been studied by deuterium and phosphorus-31 nuclear magnetic resonance (NMR) spectroscopy. The action of residual phospholipase A/sub 2/ in melittin samples resulted in mixtures of DMPC and its hydrolytic products that underwent reversible transitions at temperatures between 30 and 35/sup 0/C from extended bilayers to micellar particles which gave narrow single-line deuterium and phosphorus-31 NMR spectra. Similar transitions were observed in DMPC-myristoyllysophosphatidylcholine (lysoPC)-myristic acid mixtures containing melittin but not in melittin-free mixtures, indicating that melittin is able to stabilize extended bilayers containing DMPC and its hydrolytic products in the liquid-crystalline phase. Melittin, free of phospholipase A/sub 2/ activity, and at 3-5 mol % relative to DMPC, induced reversible transitions between extended bilayers and micellar particles on passing through the liquid-crystalline to gel phase transition temperature of the lipid, effects similar to those observed in melittin-acyl chain deuteriated dipalmitoylphosphatidylcholine (DPPC) mixtures. LysoPC at concentrations of 20 mol % or greater relative to DMPC induced transitions between extended bilayers and micellar particles with characteristics similar to those induced by melittin. It is proposed that these melittin- and lysoPC-induced transitions share similar mechanisms. The effects of melittin on the quadrupole splittings and T/sub 1/ relaxation times of head-group-deuteriated DMPC in the liquid-crystalline phase share features similar to the effects of metal ions on DPPC head groups, indicating that the conformational properties of the choline head group in PC bilayers may be affected by melittin and by metal ions in a similar manner.

  8. Phosphorus forms and chemistry in the soil profile under long-term conservation tillage: a phosphorus-31 nuclear magnetic resonance study.

    Science.gov (United States)

    Cade-Menun, Barbara J; Carter, Martin R; James, Dean C; Liu, Corey W

    2010-01-01

    In many regions, conservation tillage has replaced conventional tilling practices to reduce soil erosion, improve water conservation, and increase soil organic matter. However, tillage can have marked effects on soil properties, specifically nutrient redistribution or stratification in the soil profile. The objective of this research was to examine soil phosphorus (P) forms and concentrations in a long-term study comparing conservation tillage (direct drilling, "No Till") and conventional tillage (moldboard plowing to 20 cm depth, "Till") established on a fine sandy loam (Orthic Humo-Ferric Podzol) in Prince Edward Island, Canada. No significant differences in total carbon (C), total nitrogen (N), total P, or total organic P concentrations were detected between the tillage systems at any depth in the 0- to 60-cm depth range analyzed. However, analysis with phosphorus-31 nuclear magnetic resonance spectroscopy showed differences in P forms in the plow layer. In particular, the concentration of orthophosphate was significantly higher under No Till than Till at 5 to 10 cm, but the reverse was true at 10 to 20 cm. Mehlich 3-extractable P was also significantly higher in No Till at 5 to 10 cm and significantly higher in Till at 20 to 30 cm. This P stratification appears to be caused by a lack of mixing of applied fertilizer in No Till because the same trends were observed for pH and Mehlich 3-extractable Ca (significantly higher in the Till treatment at 20 to 30 cm), reflecting mixing of applied lime. The P saturation ratio was significantly higher under No Till at 0 to 5 cm and exceeded the recommended limits, suggesting that P stratification under No Till had increased the potential for P loss in runoff from these sites.

  9. Organic phosphorus fractionation in wetland soil profiles by chemical extraction and phosphorus-31 nuclear magnetic resonance spectroscopy

    International Nuclear Information System (INIS)

    Li, Min; Zhang, Jing; Wang, Guangqian; Yang, Haijun; Whelan, Michael J.; White, Sue M.

    2013-01-01

    Highlights: ► Chemical sequential extraction and 31 P NMR spectroscopy were used for organic P analysis. ► Organic P includes orthophosphate, monoester and diester phosphate and pyrophosphate. ► Highly resistant organic P and monoester phosphate were the dominant organic P. ► HCl pretreatment can remove most inorganic P and increase organic P recovery rate. ► A comprehensive organic P chemical sequential fractionation approach was proposed. - Abstract: Organic P (OP) plays an important role in soil P cycling and is a potential P source for wetland plants. In this study, a modified chemical sequential fractionation method and 31 P nuclear magnetic resonance spectroscopy ( 31 P NMR) of NaOH–EDTA extracts were used to examine the distribution of organic P fractions and compounds in soil profiles of the Beijing Yeyahu Wetland, China. The influence of acid treatment prior to NaOH–EDTA extraction on 31 P NMR spectra was also investigated. Results show that highly resistant OP was the major class of organic P. The rank order of organic P fractions was highly resistant OP (on average accounting for 68.5% of total OP) > moderately resistant OP (15.8%m of total OP) > moderately labile OP (11.4% of total OP) > labile OP (4.3% of total OP). Most of the organic P fractions decreased with soil depth due to the accumulation of plant residues in surface soils and the deposition and diagenesis of soils. Moderately (r = 0.586, p < 0.01) and highly (r = 0.741, p < 0.01) resistant OP fractions were positively correlated with soil organic matter. Phosphorus compounds including orthophosphate (23–74.6% of total P in spectra), monoester phosphate (18.6–76%), diester phosphate (nil-7.8%) and pyrophosphate (nil-6.7%) were characterized using 31 P NMR. Monoester-P was the dominant soil organic P compound identified. The proportion of monoester-P increased significantly in NaOH–EDTA extracts with HCl pretreatment and it was confirmed by chemical analysis. Therefore, it

  10. Development of Selective Excitation Methods in Nuclear Magnetic Resonance: Investigation of Hemoglobin Oxygenation in Erythrocytes Using Proton and Phosphorus -31 Nuclear Magnetic Resonance

    Science.gov (United States)

    Fetler, Bayard Keith

    1993-01-01

    Nuclear magnetic resonance (NMR) offers a potential method for making measurements of the percent oxygenation of hemoglobin (Hb) in living tissue non-invasively. As a demonstration of the feasibility of such measurements, we measured the percent oxygenation of Hb in red blood cells (erythrocytes) using resonances in the proton-NMR (^1H-NMR) spectrum which are characteristic of oxyhemoglobin (oxy-Hb) and deoxyhemoglobin (deoxy-Hb), and are due to the unique magnetic properties of these molecules. To perform these measurements, we developed a new NMR method of selectively exciting signals in a region of interest with uniform phase and amplitude, while suppressing the signal of the water resonance. With this method, we are able to make exact calculations distinguishing between uniform phase excitation produced at large flip-angles using the non-linear properties of the Bloch equations, and uniform phase excitation produced at small flip-angles using asymmetric pulse excitation functions. We measured the percent oxygenation of three characteristic ^1H-NMR resonances of Hb: two from deoxy-Hb, originating from the N_delta H protons of histidine residue F8, which occur at different frequencies for the alpha and beta chains of Hb; and one from oxy-Hb, originating from the gamma_2 -CH_3 protons of valine residue E11. We performed experiments both on fresh erythrocytes and on erythrocytes depleted of 2,3-diphosphoglycerate (2,3-DPG), and found that oxygen is more tightly bound to Hb in the former case. In both fresh and 2,3-DPG-depleted samples, we found that: (i) from the deoxy-Hb marker resonances, there is a small but significant difference in the oxygen saturation between the alpha and beta chains; (ii) the decrease in the areas of the deoxy-Hb marker resonances correlates well with the increase in the percent oxygenation of Hb as measured optically; (iii) the area of the oxy-Hb marker resonance may be up to ~15% less than the optically measured Hb saturation. We are

  11. Electricity utilities: Nuclear sector

    International Nuclear Information System (INIS)

    Brosche, D.

    1992-01-01

    The safe and economic operation of nuclear power plants requires an appropriate infrastructure on the part of the operator as well as a high level of technical quality of the plants and of qualification of the personnel. Added to this are a variety of services rendered by specialist firms. The Bayernwerk utility, with plants of its own, has played a major role in the development of nuclear power in the Federal Republic of Germany. The importance of nuclear power to this firm is reflected in the pattern of its electricity sources and in the composition of its power plants. (orig.) [de

  12. Managing the nuclear utility

    International Nuclear Information System (INIS)

    Williams, J.W. Jr.

    1985-01-01

    The Florida Power and Light Company (FP and L) is the fifth largest investor-owned utility in the country. The success of nuclear power generation at the St. Lucie Units 1 and 2 and Turkey Point Units 3 and 4 has resulted from a continuing management commitment to the nuclear program. The management of the power plants rely strongly on teamwork for most large projects and activities whether they entail plant operation, construction, or maintenance. Various examples of how teamwork has been used to realize the successful completion of projects or solutions to problems are given

  13. Strategy for utilizing nuclear power

    International Nuclear Information System (INIS)

    Martens, E.J.

    1977-01-01

    One of the national goals is to achieve independence in the area of energy supplies in the next few years. It is believed that attaining this goal will require extensive utilization of nuclear power in conventional fission reactors. It is proposed that the best way to develop the nuclear resource is through government ownership of the reactors. It is argued that this will minimize the risks associated with the nuclear-power option and clear the way for its exploitation

  14. Phosphorus-31 spectroscopic imaging of the human liver

    International Nuclear Information System (INIS)

    Biran, M.; Raffard, G.; Canioni, P.; Kien, P.

    1993-01-01

    During the last decade, progresses in the field of nuclear magnetic resonance spectroscopy (M.R.S.), have allowed the metabolic studies of complex biological systems. Since the coming out of whole body magnets, clinical applications are possible; they utilize magnetic field gradients coupled with selective pulse sequences. Study of the phosphorylated metabolism of human liver can be performed with sequences as ISIS, FROGS or 1D-CSI. But they present some disadvantages (for instance contamination by phosphocreatine from muscle). In the present work, we have studied the human liver in vivo by 31 P spectroscopic imaging. Several spectra could be acquired with only one acquisition. This study has needed the building of radiofrequency coils (surface coils), specially designed for liver observation (15 cm diameter 31 P coil and 19 cm diameter proton coil, both transmitter and receiver coils). Preliminary studies have been done on a phantom followed by in vivo measurements on healthy subject livers. We have obtained localized 31 P N.M.R. spectra corresponding to different voxels within the hepatic tissue. The conditions of acquisition of spectra and the problems related to the saturation of phosphorylated metabolite signals (in particular phosphodiesters) are discussed. (author). 5 figs., 15 refs

  15. Phosphorus-31 magnetic resonance spectroscopy of experimentally induced arthritis in rats

    International Nuclear Information System (INIS)

    Blatter, D.D.

    1987-01-01

    Phosphorus-31 magnetic resonance spectroscopy (MRS) of the hind paws of rats was performed at 1.5 Tesla before and during the course of an experimentally-induced inflammatory arthritis. Arthritis was induced by daily subcutaneous administration of 6-sulfanilamidoindazole, an antibacterial sulfa known to produce an acute, self-limited arthritis and periarthritis in the hind paws of rats. Phosphorus-31 spectra obtained after the development of clinical arthritis showed a significant (p 31 P MRS may permit evaluation of the severity of an inflammatory arthritis with greater accuracy than the bony changes definable by plain roentgenograms. (orig.)

  16. Managing change in nuclear utilities

    International Nuclear Information System (INIS)

    2001-07-01

    The nuclear power industry has undergone change since inception, but never so much as now. The rewards for proactively changing in anticipation of emerging demands are great, but the cost of failure is also great. Today nuclear plants are being shut down by socio-political and economic processes. The survival of the technology as a clean energy source for the future depends on the demonstration of long term safety to the public, protection of the environment, and economic superiority to competing energy sources. The overriding influence on these factors is strong management of the business with effective regulation. In particular it is necessary for both utility and regulator to believe that enhancing safety is part of being successful. This publication has been developed for all levels of management who are developing and implementing changes within their areas of responsibility. The safety conscious, continuous improvement, management culture, which has proven successful in today's nuclear business, has taken time to develop. Many utilities have difficulty sustaining this culture during the transitions that are intrinsic to change. Properly managed however, changes can enhance nuclear safety, plant reliability and cost competitiveness, from the design stage to decommissioning. Change has no respect for timing and regardless of the level of experience managers may have in its management, large scale change is confronting every nuclear utility world wide. These take the form of government policy changes, open market demands, privatization with the demand for increased shareholder returns, regulatory and social pressures, and economic and political transition. The danger from such issues for the nuclear company executive and the regulator is that they are powerful distractions, particularly for those executives who are not experienced in the unique managerial requirements of the nuclear business. This report gathers the experience of Member States into an array of

  17. Managing change in nuclear utilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The nuclear power industry has undergone change since inception, but never so much as now. The rewards for proactively changing in anticipation of emerging demands are great, but the cost of failure is also great. Today nuclear plants are being shut down by socio-political and economic processes. The survival of the technology as a clean energy source for the future depends on the demonstration of long term safety to the public, protection of the environment, and economic superiority to competing energy sources. The overriding influence on these factors is strong management of the business with effective regulation. In particular it is necessary for both utility and regulator to believe that enhancing safety is part of being successful. This publication has been developed for all levels of management who are developing and implementing changes within their areas of responsibility. The safety conscious, continuous improvement, management culture, which has proven successful in today's nuclear business, has taken time to develop. Many utilities have difficulty sustaining this culture during the transitions that are intrinsic to change. Properly managed however, changes can enhance nuclear safety, plant reliability and cost competitiveness, from the design stage to decommissioning. Change has no respect for timing and regardless of the level of experience managers may have in its management, large scale change is confronting every nuclear utility world wide. These take the form of government policy changes, open market demands, privatization with the demand for increased shareholder returns, regulatory and social pressures, and economic and political transition. The danger from such issues for the nuclear company executive and the regulator is that they are powerful distractions, particularly for those executives who are not experienced in the unique managerial requirements of the nuclear business. This report gathers the experience of Member States into an array of

  18. Phosphorus-31 NMR analysis of gold plating baths

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.E.

    1992-03-01

    This report describes the nuclear magnetic resonance (NMR) analysis of gold plating baths in the Micro-Miniature Electronic Assembly department of Allied-Signal Inc., Kansas City Division (KCD). The baths were analyzed for phosphorylated components. In freshly prepared gold plating baths in this department the principle compound observed is aminotrimethyl-phosphonate, or ATMP. As the bath is used in production, the ATMP breaks down; and new compounds, aminodimethylphosphonate (ADMP), aminomonomethylphosphonate, (AMMP), and inorganic phosphate (H{sub 2}PO{sub 4}{sup {minus}}), are formed. The NMR method has been used for almost three years to monitor the concentrations of the ATMP and breakdown products. In a previous report, results from January through October 1988 were reported. In this report, results from November 1988 through January 1991 are given.

  19. Experience with nuclear fuel utilization in Bulgaria

    Energy Technology Data Exchange (ETDEWEB)

    Harizanov, Y [Committee on the Use of Atomic Energy for Peaceful Purposes, Sofia (Bulgaria)

    1997-12-01

    The presentation on experience with nuclear fuel utilization in Bulgaria briefly reviews the situation with nuclear energy in Bulgaria and then discusses nuclear fuel performance (amount of fuel loaded, type of fuel, burnup, fuel failures, assemblies deformation). 2 tabs.

  20. Utilization of nuclear research reactors

    International Nuclear Information System (INIS)

    1980-01-01

    Full text: Report on an IAEA interregional training course, Budapest, Hungary, 5-30 November 1979. The course was attended by 19 participants from 16 Member States. Among the 28 training courses which the International Atomic Energy Agency organized within its 1979 programme of technical assistance was the Interregional Training Course on the Utilization of Nuclear Research Reactors. This course was held at the Nuclear Training Reactor (a low-power pool-type reactor) of the Technical University, Budapest, Hungary, from 5 to 30 November 1979 and it was complemented by a one-week Study Tour to the Nuclear Research Centre in Rossendorf near Dresden, German Democratic Republic. The training course was very successful, with 19 participants attending from 16 Member States - Bangladesh, Bolivia, Czechoslovakia, Ecuador, Egypt, India, Iraq, Korean Democratic People's Republic, Morocco, Peru, Philippines, Spain, Thailand, Turkey, Vietnam and Yugoslavia. Selected invited lecturers were recruited from the USA and Finland, as well as local scientists from Hungarian institutions. During the past two decades or so, many research reactors have been put into operation around the world, and the demand for well qualified personnel to run and fully utilize these facilities has increased accordingly. Several developing countries have already acquired small- and medium-size research reactors mainly for isotope production, research in various fields, and training, while others are presently at different stages of planning and installation. Through different sources of information, such as requests to the IAEA for fellowship awards and experts, it became apparent that many research reactors and their associated facilities are not being utilized to their full potential in many of the developing countries. One reason for this is the lack of a sufficient number of trained professionals who are well acquainted with all the capabilities that a research reactor can offer, both in research and

  1. Are American utilities sorry they went nuclear

    International Nuclear Information System (INIS)

    Dallaire, E.E.

    1981-01-01

    The future of nuclear power in the U.S. will be determined in large measure by what the electric utilities decide to do. Very few electric utilities are planning to build more nuclear power plants. Most utilities feel the 12 to 14 years it takes to build a nuclear plant is simply too long, especially when construction money must be borrowed at record interest rates. Also, there are too many uncertainties regarding what an acceptable plant design is. On the other hand, these utilities also strongly believe that the U.S. needs nuclear power and that it would be imprudent for a utility to put all its energy eggs in one basket, coal

  2. Meeting nuclear utilities manpower needs

    International Nuclear Information System (INIS)

    Sillin, L.F. Jr.

    1982-01-01

    The nuclear-power industry must attract and train 57,000 employees during the next decade, according to a survey which found a high rate of personnel turnover, 8790 unfilled positions, and 75 new plants scheduled to come on line. The Institute of Nuclear Power Operators (INPO) and the industry need to address personnel planning to find out how to meet these needs. Studies indicate a history of on-site staffing and training deficiencies. Regulatory requirements also contribute to manpower shortages. This article examines manpower problems and suggests initiatives the industry can take to support educational programs, expand training, provide employee incentives, and pool technical resources. 7 tables

  3. To the problem of utilization of nuclear submarines

    International Nuclear Information System (INIS)

    Tarakanov, E.; Larin, V.

    1999-01-01

    Paper discusses a concept of step-by-step utilization of nuclear submarines in Russia. By the late 2000 minimum 160 nuclear submarines with over 300 nuclear reactors should be removed. Unloading of spent nuclear fuel from reactors, dismounting of nuclear submarines, efforts to arrange storage facilities for liquid and solid radioactive waste are the main steps of nuclear submarine utilization. Under the rates of nuclear submarine utilization being as they are, the utilization of 160 nuclear submarines will take about 30 years. Paper analyzes the alternative variants of nuclear submarine utilization and discusses the social and ecological aspects of utilization of nuclear submarines [ru

  4. Restructuring of Canada's nuclear utilities: recent developments

    International Nuclear Information System (INIS)

    Guindon, S.

    1998-01-01

    Business decisions relating to the electric power sector are a provincial responsibility in Canada. The federal government looks to the three nuclear utilities to manage their nuclear assets and maintain them in a way that maximizes their reliability, efficiency and overall performance. A significant development in Canada's nuclear sector in the past year was the Ontario Hydro Nuclear Asset Optimization Plan. Structural change in the North American electricity market is a major impetus for decisions regarding nuclear assets by Canada's electric power utilities. The Ontario government is now taking steps to introduce competition in the Ontario Electricity market. The province of New Brunswick, which has one reactor at Point Lepreau which supplies one-third of the province's electricity, is also taking measures to introduce competition in its electricity market. (author)

  5. Material degradation - a nuclear utility's view

    International Nuclear Information System (INIS)

    Spekkens, P.

    2007-01-01

    Degradation of nuclear plant materials has been responsible for major costs and unit outage time. As such, nuclear utilities are important end users of the information produced by R and D on material degradation. This plenary describes the significance of material degradation for the nuclear utilities, and how utilities use information about material degradation in their short, medium and long term planning activities. Utilities invest in R and D programs to assist them in their business objective of operating safely, reliably and cost competitively. Material degradation impacts all three of these business drivers. Utilities make decisions on life cycle planning, unit refurbishment and 'new build' projects on the basis of their understanding of the behaviour of a variety of materials in a broad range of environments. The R and D being carried out today will determine the future business success of the nuclear utilities. The R and D program needs to be broadly based to include a range of materials, environments and time-frames, particularly any new materials proposed for use in new units. The R and D community needs to help the utility managers make choices that will result in an optimized materials R and D program

  6. Nuclear utility structure. Use of nuclear service companies

    International Nuclear Information System (INIS)

    Ring, L.E.

    1980-01-01

    The feasibility of utilities incorporating service companies to construct and maintain nuclear power plants is analyzed. Responsibilities of the service companies and the public opinion of the concept are discussed

  7. The study of human organs by phosphorus-31 topical magnetic resonance spectroscopy

    International Nuclear Information System (INIS)

    Oberhaensli, R.D.; Galloway, G.J.; Hilton-Jones, David; Bore, P.J.; Styles, Peter; Rajagopalan, Bheeshma; Taylor, D.J.; Radda, G.K.

    1987-01-01

    The potential clinical use of topical magnetic resonance spectroscopy (volume selection by static magnetic field gradients) was tested in 50 studies in volunteers. Topical magnetic resonance spectroscopy (MRS) was shown to be a straightforward method for localising 31 P spectra of brain and liver. However, the spherical shape and fixed position of the selected volume posed serious limitations to the study of heart and transplanted kidney by topical MRS. Phosphorus-31 spectra of approx. 30 cm -3 of brain or liver could be obtained in 8 min. Ratios of metabolite concentrations could be determined with a coefficient of variation ranging from 10% to 30%. The ratios of phosphocreatine/ATP and inorganic phosphate/ATP in brain were 1.8 and 0.3, respectively. The ratio of inorganic phosphate/ATP in liver was 0.9. Intracellular pH was 7.03 in brain and 7.24 in liver. The T 1 relaxation times of phosphocreatine, inorganic phosphate and γ-ATP in brain were 4.8 s, 2.5 s and 1.0 s, respectively. (author)

  8. Transport and phosphorylation of choline in higher plant cells. Phosphorus-31 nuclear magnetic resonance studies

    Energy Technology Data Exchange (ETDEWEB)

    Bligny, R.; Foray, M.F.; Roby, C.; Douce, R.

    1989-03-25

    When sycamore cells were suspended in basal medium containing choline, the latter was taken up by the cells very rapidly. A facilitated diffusion system appertained at low concentrations of choline and exhibited Michaelis-Menten kinetics. At higher choline concentrations simple diffusion appeared to be the principal mode of uptake. Addition of choline to the perfusate of compressed sycamore cells monitored by /sup 31/P NMR spectroscopy resulted in a dramatic accumulation of P-choline in the cytoplasmic compartment containing choline kinase and not in the vacuole. The total accumulation of P-choline over a 10-h period exhibited Michaelis-Menten kinetics. During this period, in the absence of Pi in the perfusion medium there was a marked depletion of glucose-6-P, and the cytoplasmic Pi resonance disappeared almost completely. When a threshold of cytoplasmic Pi was attained, the phosphorylation of choline was sustained by the continuous release of Pi from the vacuole although at a much lower rate. However, when 100 microM inorganic phosphate was present in the perfusion medium, externally added Pi was preferentially used to sustain P-choline synthesis. It is clear, therefore, that cytosolic choline kinase associated with a carrier-mediated transport system for choline uptake appeared as effective systems for continuously trapping cytoplasmic Pi including vacuolar Pi entering the cytoplasm.

  9. Altered phospholipid metabolism in schizophrenia: a phosphorus 31 nuclear magnetic resonance spectroscopy study.

    Science.gov (United States)

    Weber-Fahr, Wolfgang; Englisch, Susanne; Esser, Andrea; Tunc-Skarka, Nuran; Meyer-Lindenberg, Andreas; Ende, Gabriele; Zink, Mathias

    2013-12-30

    Phospholipid (PL) metabolism is investigated by in vivo 31P magnetic resonance spectroscopy (MRS). Inconsistent alterations of phosphocholine (PC), phosphoethanolamine (PE), glycerophosphocholine (GPC) and glycerophosphoethanolamine (GPE) have been described in schizophrenia, which might be overcome by specific editing techniques. The selective refocused insensitive nuclei-enhanced polarization transfer (RINEPT) technique was applied in a cross-sectional study involving 11 schizophrenia spectrum disorder patients (SZP) on stable antipsychotic monotherapy and 15 matched control subjects. Metabolite signals were found to be modulated by cerebrospinal fluid (CSF) content and gray matter/brain matter ratio. Corrected metabolite concentrations of PC, GPC and PE differed between patients and controls in both subcortical and cortical regions, whereas antipsychotic medication exerted only small effects. Significant correlations were found between the severity of clinical symptoms and the assessed signals. In particular, psychotic symptoms correlated with PC levels in the cerebral cortex, depression with PC levels in the cerebellum and executive functioning with GPC in the insular and temporal cortices. In conclusion, after controlling for age and tissue composition, this investigation revealed alterations of metabolite levels in SZP and correlations with clinical properties. RINEPT 31P MRS should also be applied to at-risk-mental-state patients as well as drug-naïve and chronically treated schizophrenic patients in order to enhance the understanding of longitudinal alterations of PL metabolism in schizophrenia. Copyright © 2013 Elsevier Ireland Ltd. All rights reserved.

  10. Phosphorus-31 and proton magnetic resonance spectroscopy of the medial temporal region in schizophrenic patients

    International Nuclear Information System (INIS)

    Yamada, Koichiro

    1996-01-01

    Phosphorus-31 magnetic resonance spectroscopy (MRS) was performed 22 schizophrenic patients and in 22 healthy volunteers. Psychiatric symptoms were estimated on the Brief Psychiatric Rating Scale (BPRS), the Scale for the Assessment of Negative Symptoms (SANS) and the Scale for the Assessment of Positive Symptoms (SAPS). The spectra were quantified for phosphomonoesters (PME), inorganic orthophosphate (Pi), phosphodiesters (PDE), phosphocreatine (Pcr) and the γ, α and β phosphates of 5'-adenosine triphosphate (ATP) by peak area measurements. Proton MRS was performed in 15 schizophrenic patients and in 15 healthy volunteers. Psychiatric symptoms were estimated on the Positive and Negative Syndrome Scale (PANSS) and the SANS. The spectra of N-acetylates (NA), choline-containing compounds (Cho) and creatine-phosphocreatine (Cr) were quantified. The patients showed an increase in the % PDE and a decrease in the % β-ATP in the left temporal region. Positive correlations were found between the % PDE and the subscale of positive symptoms on the BPRS and the total score of SAPS. The % β-ATP correlated negatively with the total score on SAPS. The NA/Cho and NA/Cr ratios were significantly lower in patients than in normal subjects. The Cho/Cr ratio was higher in the patient group. The age at onset of illness correlated positively with the NA/Cho and NA/Cr ratios. No significant correlations were observed between the ratios of metabolites and the scores of PANSS and SANS. There were no significant associations between the mole percentages and the ratios and the daily doses of neuroleptics and anticholinergics. These findings suggest that the disturbed membrane phospholipid and high-energy phosphate metabolism in the left medial temporal region may be one of the pathophysiologies of neuroleptic-resistant positive symptoms in schizophrenia and these abnormalities may be related to neuronal loss and/or neuronal dysfunction in this region. (H.O.)

  11. Utilities' nuclear fuel economic evaluation methods

    International Nuclear Information System (INIS)

    Sonz, L.A.

    1987-01-01

    This paper presents the typical perceptions, methods, considerations, and procedures used by an operating electric utility in the economic evaluation of nuclear fuel preparation and utilization scenarios. The means given are probably not an exclusive review of those available, but are the author's recollection of systems employed to select and recommend preferable courses of action. Economic evaluation of proposed nuclear fuel scenarios is an important, but not exclusive, means of deciding on corporate action. If the economic evaluation is performed and coordinated with the other corporate considerations, such as technical and operational ability, electrical system operations management, tax effects, capital management, rates impact, etc., then the resultant recommendation may be employed to the benefit of the customers and, consequently, to the corporation

  12. Implementation digital technologies in nuclear utilities

    International Nuclear Information System (INIS)

    Wiegand, C.; Maselli, A.J.

    2012-01-01

    The introduction of digital technologies into the nuclear industry has assisted in many ways and made many of the Life Extensions and Uprates a possibility. But with this introduction of digital technologies comes some potentially challenging issues which need to be addressed for ultimate project success. This presentation discusses what a nuclear utility should consider and establish when implementing digital technologies in their plant. Digital technologies have been employed in many safety critical industries such as Aerospace, Pharmaceutical, Oil and Gas, and Chemical. However, nuclear industry implementation of digital technologies has been slow and in many ways tenuous. There are even documented operating experience events in which plant trips/SCRAMs occurred during a digital system implementation. This presentation aims to prevent those issues drawing upon the lessons learned over the past 5 years. Considerations include general challenges to overcome when implementing Digital Technologies, how to justify and execute projects, evaluation of resource knowledge, and the new challenges of Cyber Security. (author)

  13. Implementation digital technologies in nuclear utilities

    Energy Technology Data Exchange (ETDEWEB)

    Wiegand, C.; Maselli, A.J., E-mail: Tony.Maselli@Invensys.com [Invensys Operations Management, London (United Kingdom)

    2012-07-01

    The introduction of digital technologies into the nuclear industry has assisted in many ways and made many of the Life Extensions and Uprates a possibility. But with this introduction of digital technologies comes some potentially challenging issues which need to be addressed for ultimate project success. This presentation discusses what a nuclear utility should consider and establish when implementing digital technologies in their plant. Digital technologies have been employed in many safety critical industries such as Aerospace, Pharmaceutical, Oil and Gas, and Chemical. However, nuclear industry implementation of digital technologies has been slow and in many ways tenuous. There are even documented operating experience events in which plant trips/SCRAMs occurred during a digital system implementation. This presentation aims to prevent those issues drawing upon the lessons learned over the past 5 years. Considerations include general challenges to overcome when implementing Digital Technologies, how to justify and execute projects, evaluation of resource knowledge, and the new challenges of Cyber Security. (author)

  14. Electric utility deregulation - A nuclear opportunity

    International Nuclear Information System (INIS)

    DeMella, J.R.

    2002-01-01

    influenced and ultimately determined the price or tariffs for electricity to customers, were generally the same. Utilities revenue requirements were founded upon complex 'cost of service' formulas which emphasized and allowed the recovery of all 'reasonable' costs including operating expenses, taxes, depreciation of investments and additionally assured a reasonable rate or return on all outstanding investments. The consequence was that, through regulation of electric rate design, the ultimate price of electricity was determined by the aggregate of costs to produce it, independent of the forces of supply and demand. Through the examination of the major principles and features of regulated compared to unregulated electric markets such as the 'obligation to serve' and the 'cost of service', this presentation will address and discuss the economic opportunities and risks associated with nuclear power plants operating in deregulated, competitive electric generation markets. In transitioning to competitive markets, a number of key economic questions will be raised that will emphasize nuclear plant economic requirements for a profitable enterprise, addressing factors such as, plant operating performance, market conditions, energy price, key economic measures, investment opportunities, nuclear asset valuation and plant life extension. An economic analysis of a recent nuclear power plant valuation study will be presented including a discussion of key input variables, financial assumptions, economic results and a brief demonstration of an interactive, PC based computer model used for the analysis. A similar model, is currently being considered by the IAEA to evaluate the economics of nuclear power plant life extension along with alternative generation approaches. In closing, a number of short and long term prospects for the future of nuclear power will be discussed including plant life extension and the prognostication of a new electric generation business model concept

  15. Nuclear fuel utilization in Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

    Boyadzhiev, Z; Kharalampieva, Ts; Pejchinov, Ts [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

    1994-12-31

    An assessment of fuel utilization in Kozloduy NPP units 1-6 is made on the basis of operational data obtained for a total of 62 fuel cycles. Basic characteristics of core loading and operation conditions are given. SPPS-1 and BIPR-7 codes are used to calculate assembly-wise power distributions for different full power days of a given cycle and unit. The data are compared with the measured values of these quantities. The analysis performed shows that the core loading option chosen has led to efficient fuel utilization without violation of the nuclear safety criteria. For WWER-440 (Units 1 - 4) this is expressed in effective reduction of the reactor vessel irradiation, maintaining the design duration of the fuel cycles at a reduced number of assemblies by a factor 5 - 5-10%, utilizing fuel with higher enrichment and implementing the 4-year fuel cycle. For WWER-1000 the improvements lead to: adoption of the 3-year fuel cycle utilizing fuel with 4.4% initial enrichment, implementation of improved fuel with a new type of absorbers and more effective low-leakage core loading patterns. 10 tabs., 6 figs., 7 refs.

  16. Utility and risk of nuclear energy

    International Nuclear Information System (INIS)

    Barnert, H.; Borsch, P.; Feldmann, A.; Merz, E.; Muench, E.; Oesterwind, D.; Voss, A.; Wolters, J.

    1979-09-01

    The present report contains lectures of a seminar that was arranged by the programme group nuclear power and environment of the Kernforschungsanlage Juelich . The items were: 1) Do we need nuclear energy. An attempt at a system analytic answer. 2) Energy production by means of nuclear fission. 3) The nuclear power plants. 4) Nuclear energy and radiation hazard. 5) Safety of nuclear power plants. (RW) [de

  17. Study of the muscular metabolism using Phosphorus 31 Magnetic Resonance Spectroscopy (31P-MRS) in normal subjects

    International Nuclear Information System (INIS)

    Batista, T.S.; Salmon, C.E.G.; Santos, A.C.

    2008-01-01

    Phosphorus 31 Magnetic Resonance Spectroscopy ( 31 P-MRS) is a powerful technique for evaluating human muscular metabolism. Some reports indicated the behavior of phosphorylated metabolites (PCr, ADP and Pi) and other indirect parameters (intracellular pH and [Mg 2+ ]) in muscles at rest and after an exercise load. The aim of this work is a quantitative study of the phosphorylated metabolite levels in the calf muscle of normal subjects at rest and post-exercise, in order to create a normal control database. 31 P spectra of seven volunteers were acquired in both conditions. Firstly, different quantification methodologies were evaluated to use the more reliable. The P Cr metabolite was the more stable at rest and it had mono-exponential behavior after exercise. The Pi was the more sensible indicator of the physical activities. The time constants of the recuperation process are report for all the evaluated metabolites and parameters. Finally, the temporal behavior of phospho monoesters was quantified. (author)

  18. Nuclear H2 production - a utility perspective

    International Nuclear Information System (INIS)

    Keuter, D.

    2010-01-01

    Entergy is the second largest nuclear owner/operator in the United States with five nuclear units in the south operating under a cost of service structure and an additional six units in the Northeast and Midwest operating as merchant generating facilities. As a major nuclear operator in the merchant sector, Entergy wears the risk of nuclear operations - revenues are directly dependent upon operational performance. Our investment in merchant nuclear operations reflects our belief that use of nuclear energy in the competitive merchant environment can be an economically viable business venture. Over the past 10 years, our success in the merchant sector has led to our support for the expanded use of nuclear energy and more specifically the development and deployment of advanced nuclear technologies. Of particular interest today is Entergy's support for the development of HTGR - nuclear technologies that can expand the application of nuclear energy into the broader energy marketplace. Studies and economic evaluations, thus far, have indicated that HTGR can compete with premium fossil fuels in supplying process heat for industrial processes and may well become competitive in the production of hydrogen for the bulk market. We believe that the application of nuclear energy in the broader energy marketplace is of vital importance to our nation's energy security and as an experienced merchant nuclear operator, we believe that business opportunities in this broader energy market will emerge. (author)

  19. Operation and utilizations of Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    Hien, P.Z.

    1988-01-01

    The reconstructed Dalat nuclear research reactor was commissioned in March 1984 and up to September 1988 more than 6200 hours of operation at nominal power have been recorded. The major utilizations of the reactor include radioisotope production, activation analysis, nuclear data research and training. A brief review of the utilizations of the reactor is presented. Some aspects of reactor safety are also discussed. (author)

  20. Nuclear snow job: utilities struggle to avoid credibility meltdown

    International Nuclear Information System (INIS)

    Feeney, A.

    1979-01-01

    Electric utilities and the US nuclear industry are criticized for giving a public relations response to safety concerns following the accident at Three Mile Island and for passing the cost of the response on to utility customers. The large amounts of money budgeted by Babcock and Wilcox, Bechtel Power Corporation, the Atomic Industrial Forum, Electric Power Research Institute, Nuclear Energy Women, and others to minimize the incident and counter anti-nuclear arguments with media events are seen here by Feeney as evidence that the utilities and nuclear industry are afraid of political consequences as their technical credibility vanishes

  1. European Utility Requirements: European nuclear energy

    International Nuclear Information System (INIS)

    Komsi, M.; Patrakka, E.

    1997-01-01

    The work procedure and the content of the European Utility Requirements (EUR) concerning the future LWRs is described in the article. European Utility Requirements, produced by utilities in a number of European countries, is a document specifying the details relating to engineered safety, operating performance, reliability and economics of the reactors to be built by manufacturers for the European market

  2. The impact of computers on the nuclear utility industry

    International Nuclear Information System (INIS)

    Taylor, J.J.

    1984-01-01

    The applications of computer technology to the nuclear utility industry are discussed in light of recent phenomenal growth of computer hardware and software. Computer applications in existence in the power plants are presented, as well as potential future development for plant design, construction, operation, maintenance and retrofit. Utility concerns are addressed. The study concludes that the applications of computer technology to the nuclear utility industry are highly promising and evolutionary in nature

  3. Nuclear utilities must cut costs: ANS meeting

    International Nuclear Information System (INIS)

    Taylor, G.M.

    1993-01-01

    This article looks at cost factors in the nuclear industry, and concludes that the nuclear industry must be very careful with its operations and maintenance (O ampersand M) costs in particular to stay competitive in the energy marketplace. These costs have been rising at 5% per year lately, and are becoming a major cost for the nuclear industry. Analysts feel that a major reason for these increases is the responsibility of management. The article highlights the need to tighten the cost factors or face the loss of market share

  4. Nuclear utility education and training becoming too plant specific?

    International Nuclear Information System (INIS)

    Wicks, F.

    1986-01-01

    As the Supervisor of a university nuclear reactor and operations curriculum, the author has also been offering education and training programs for nuclear utility technical support and operations personnel. Similar results have been reported by other universities offering similar programs. These programs also provide very important benefits to university nuclear engineering departments in terms of much needed revenues during this time of declining student enrollment and also by the information flow from the nuclear utility participants to the university personnel, which can yield both improved courses and identify research opportunities. University programs serve an important complementary function to plant-specific programs and should be continued and supported

  5. Utility business analyses often overlook nuclear strengths

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    It is argued that economic comparisons of nuclear with fossil-fuelled electricity generation may err if they neglect socioeconomic factors such as employment, secondary effects on prices, and the goals of national and provincial self-sufficiency

  6. Building Foundations for Nuclear Security Enterprise Analysis Utilizing Nuclear Weapon Data

    Energy Technology Data Exchange (ETDEWEB)

    Josserand, Terry Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Security Enterprise and Cost Analysis; Young, Leone [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Security Enterprise and Cost Analysis; Chamberlin, Edwin Phillip [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Security Enterprise and Cost Analysis

    2017-09-01

    The Nuclear Security Enterprise, managed by the National Nuclear Security Administration - a semiautonomous agency within the Department of Energy - has been associated with numerous assessments with respect to the estimating, management capabilities, and practices pertaining to nuclear weapon modernization efforts. This report identifies challenges in estimating and analyzing the Nuclear Security Enterprise through an analysis of analogous timeframe conditions utilizing two types of nuclear weapon data - (1) a measure of effort and (2) a function of time. The analysis of analogous timeframe conditions that utilizes only two types of nuclear weapon data yields four summary observations that estimators and analysts of the Nuclear Security Enterprise will find useful.

  7. Utilities' view on the fuel management of nuclear power plants

    International Nuclear Information System (INIS)

    Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

    1977-01-01

    Utilities engagement in nuclear power requires an increasing amount of fuel management activities by the utilities in order to meet all tasks involved. These activities comprise essentially two main areas: - activities to secure the procurement of all steps of the fuel cycle from the head to the back end; - activities related to the incore fuel managment. A general survey of the different steps of the nuclear fuel cycle is presented together with the related activities and responsibilities which have to be realized by the utilities. Starting in the past, today's increasing utility involvement in the nuclear fuel management is shown, as well as future fuel management trends. The scope of utilities' fuel management activities is analyzed with respect to organizational aspects, technical aspects, safeguarding aspects, and financial aspects. Utilities taking active part in the fuel management serves to achieve high availability and flexibility of the nuclear power plant during the whole plant life as well as safe waste isolation. This can be assured by continuous optimization of all fuel management aspects of the power plant or on a larger scale of a power plant system, i.e., utility activities to minimize the effects of fuel cycle on the environment, which includes optimization of fuel behaviour, radiation exposure to public and personnel, and utility technical and economic evaluations of out- and incore fuel management. These activities of nuclear power producing utilities in the field of nuclear fuel cycle are together with a close cooperation with fuel industry as well as national and international authorities a necessary basis for the further utilization of nuclear power

  8. The Nuclear Magnetic Resonance and its utilization in image formation

    International Nuclear Information System (INIS)

    Bonagamba, T.J.; Tannus, A.; Panepucci, H.

    1987-01-01

    Some aspects about Nuclear Magnetic Resonance (as Larmor Theorem, radio frequency pulse, relaxation of spins system) and its utilization in two dimensional image processing with the necessity of a tomography plane are studied. (C.G.C.) [pt

  9. Arguments against the utilization of nuclear energy

    International Nuclear Information System (INIS)

    1982-05-01

    The attempt is made to treat the subject 'nuclear energy' on a large scale. In this brochure, all important problems can only be discussed quite briefly; a great number of footnotes indicating further literature shall guide the reader to thorough study. The text is supposed to serve as a systematic introduction to the problems as well as for looking up individual partial aspects. A lot of space has been given to the presentation of those aspects that concern the risk of nuclear facilities, and the threat to man and environment by their operation. Moreover, fundamental political, scientific-sociological, economic and other social problems are discussed. The objective of this was to give the reader an idea of the social background before which the controversy about the nuclear energy is taking place today and what factors decide its development. (orig./HP) [de

  10. Deregulation of the electric utility industry - implications for nuclear power

    International Nuclear Information System (INIS)

    Fern, A.Rose

    2000-01-01

    The deregulation movement sweeping the international electric utility community represents a dramatic shift om the traditional business model of utilities. This paper will focus on deregulation in thc United States and the new challenges for nuclear power plant operators. An overview of the new operating models being implemented in the US will lead into a discussion on new economic and operating concerns for nuclear power plant operators. (author)

  11. Deregulation of the electric utility industry - implications for nuclear power

    International Nuclear Information System (INIS)

    Fern, A.R.

    2001-01-01

    The deregulation movement sweeping the international electric utility community represents a dramatic shift from the traditional utility business model. This paper will focus on deregulation in the United States and the new challenges for nuclear power plant operators. An overview of the new operating models being implemented in the US will lead into a discussion on new economic and operating concerns for nuclear power plant operators. (author)

  12. Long-range goal setting in the nuclear utility industry

    International Nuclear Information System (INIS)

    Beard, P.M.

    1986-01-01

    The Institute of Nuclear Power Operation's (INPO's) programs support the industry's efforts to improve performance in nuclear plant safety and reliability. The success of these programs can best be measured by the progress of the industry. As utilities focused their attention on nuclear plant performance, the Institute's goal was to make sure its programs and activities provided the best possible support for these efforts. INPO continues to coordinate an industry-wide plant performance indicator program to assist member utilities in assessing station performance. Closely related to this effort is the nuclear industry's establishment of long-range plant performance goals. The US nuclear utility industry currently sends INPO quarterly data on 28 key performance indicators. INPO analyzes these data and provides periodic reports to its members and participants. Selected highlights of INPO's Performance Indicators for the US Nuclear Utility, dated June 1986, are discussed. Throughout 1985, INPO interacted with members, participants, and three external ad hoc review groups to refine the overall performance indicators and to develop background for each unit. By April 1986, each utility had developed long-term goals for each unit. By April 1986, each utility had developed long-term goals for most of the overall indicators. These goals represent a commitment to achievement of excellence when applied to the day-to-day conduct of plant operations, and provide a framework for action

  13. A method of short range system analysis for nuclear utilities

    International Nuclear Information System (INIS)

    Eng, R.; Mason, E.A.; Benedict, M.

    1976-01-01

    An optimization procedure has been formulated and tested that is capable of solving for the optimal generation schedule of several nuclear power reactors in an electric power utility system, under short-range, resource-limited, conditions. The optimization procedure utilizes a new concept called the Opportunity Cost of Nuclear Power (OCNP) to optimally assign the resource-limited nuclear energy to the different weeks and hours in the short-range planning horizon. OCNP is defined as the cost of displaced energy when optimally distributed nuclear energy is marginally increased. Under resource-limited conditions, the short-range 'value' of nuclear power to a utility system is not its actual generation cost, but the cost of the next best alternative supply of energy, the OCNP. OCNP is a function of a week's system reserve capacity, the system's economic loading order, the customer demand function, and the nature of the available utility system generating units. The optimized OCNP value of the short-range planning period represents the utility's short-range energy replacement cost incurred when selling nuclear energy to a neighbouring utility. (author)

  14. Economics and utilization of thorium in nuclear reactors

    International Nuclear Information System (INIS)

    1978-05-01

    Information on thorium utilization in power reactors is presented concerning the potential demand for nuclear power, the potential supply for nuclear power, economic performance of thorium under different recycle policies, ease of commercialization of the economically preferred cases, policy options to overcome institutional barriers, and policy options to overcome technological and regulatory barriers

  15. Utilization of nuclear technology to ship

    International Nuclear Information System (INIS)

    Kim, H. C.

    2004-01-01

    The SMART, a medium sized power plant with an output of 330mwth, can be used on barges to generate electric power and water, and can be used to propel container ships. For high speed, to secure the container cargo, and huge container carriers, to lower the operating expenses, the use of nuclear power reactor is essential. To compete in this challenging area with the advanced countries, a well-orchestrated joint effort will be necessary by the government and the industries

  16. Utilities respond to nuclear station blackout rule

    International Nuclear Information System (INIS)

    Rubin, A.M.; Beasley, B.; Tenera, L.P.

    1990-01-01

    The authors discuss how nuclear plants in the United States have taken actions to respond to the NRC Station Blackout Rule, 10CFR50.63. The rule requires that each light water cooled nuclear power plant licensed to operate must be able to withstand for a specified duration and recover from a station blackout. Station blackout is defined as the complete loss of a-c power to the essential and non-essential switch-gear buses in a nuclear power plant. A station blackout results from the loss of all off-site power as well as the on-site emergency a-c power system. There are two basic approaches to meeting the station blackout rule. One is to cope with a station blackout independent of a-c power. Coping, as it is called, means the ability of a plant to achieve and maintain a safe shutdown condition. The second approach is to provide an alternate a-c power source (AAC)

  17. Analysis and planning of the utilization of nuclear power plants

    International Nuclear Information System (INIS)

    Skvarka, P.

    1985-01-01

    The utilization coefficient as one of the characteristics of availability of nuclear power plants and the operation results (like maximum power, block number, and electric energy generation) are investigated by different statistic methods for several nuclear power plants with PWR type reactors and compared with those of WWER 440-type reactors. By means of linear many-parameter regression analysis the utilization coefficient is studied in dependence on block power and time after reactor commissioning. Forecastings of mean utilization coefficients are presented for the power of WWER 1000-type reactors

  18. Nuclear submarine utilization. Financial deadlock and search for its output

    International Nuclear Information System (INIS)

    Dovgusha, V.V.; Tikhonov, M.N.

    1995-01-01

    Program of nuclear submarine utilization in the Russian Federation is described. The program provides for complete solution of all problems, connected with nuclear submarine utilization, including reconstruction of ship-repair and ship-cutting plants, metal fabrication plants, construction of points of temporary radioactive waste storages, new burials, as well as required social support of personnel, working under unhealthy conditions. The program is based on guaranteed and sufficient financing from extra-budgetary sources, as well as on new technologies, enabling to utilize all written off ships during 10-15 years

  19. Basic plan for nuclear power development and utilization in 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This report presents specific measures to be carried out in 1987 to promote research, development and application of nuclear power. The first part deals with the strengthening of safety measures, centering on the improvement in regulation and administration for nuclear power safety; promotion of safety studies; improvement and strengthening of disaster prevention measures; improvement and strengthening of environmental activity surveys; improvement in exposure control measures for nuclear power operation workers; and establishment of the nuclear fuel cycle and safety in such activities as development of new reactors. The second part of the report addresses the promotion of nuclear power generation. Measures for this will be focused on the promotion of location of nuclear power plants and the development of advanced technology for light water reactors. The third part describes measures for establishing the nuclear fuel cycle, which cover the procurement of uranium resources; enrichment of uranium; reprocessing of spent fuel and utilization of plutonium and recovered uranium; and disposal of radioactive waste. Other parts presents measures to be carried out for the development of new power reactors; research on nuclear fusion; development of nuclear powered vessels; application of radiations; improvement in the infrastructure for nuclear power development and utilization; etc. (Nogami, K.)

  20. Analysis of nuclear fuel utilization strategies

    International Nuclear Information System (INIS)

    Souza, J.A.M. de; Rubini, L.A.; Silva, R.P.

    1981-01-01

    Having in mind a rational utilization of the national uranium reserves, in the alternatives considered here in both the recycling of irradiated fuel and the introduction of fast breeder reactors (FBR's) in the electric energy generation system are analyzed. Present thermal reactors (PWR's) would be, thus, gradually replaced, and the plutonium produced by them used as fuel for the next generation of FBR's. (Author) [pt

  1. Beneficial utilization of nuclear waste products

    International Nuclear Information System (INIS)

    Dix, G.P.

    1975-01-01

    A sufficient supply of isotopes exists to conduct demonstrational experiments in the 1975-1980 time frame to stimulate a market for waste products. A large potential market exists for a number of waste products, measured in terms of billions of dollars. Actinide by-products can become a feed stock for producing other energy producing isotopes by neutron irradiation whose value may exceed that of the fission products. Commercial reprocessors will not invest in the extraction and separation of isotopes from the waste stream until a proven market has evolved. Economic studies must be performed to establish the trade-offs between the beneficial use or disposal of wastes. Fundamental to these studies are process economics, safety analyses applications studies, and market analyses, both domestic and foreign. Regardless of the degree of beneficial utilization of wastes, some residual material from wastes not utilized and spent by-products after utilization will have to undergo ultimate disposal. Isotopic waste products have the potential for solving a number of societal and national security problems and represent a unique source of energy and materials

  2. Viewpoint of utilities regarding fuel management of nuclear power plants

    International Nuclear Information System (INIS)

    Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

    1977-01-01

    The engagement of utilities in nuclear power requires them to engage in an increasing amount of fuel management activities in order to carry out all the tasks involved. Essentially, these activities involve two main areas: The procurement of all steps of the fuel cycle from the head to the back end; and in-core fuel management. A general survey of the different steps of the nuclear fuel cycle is presented together with the related activities and responsibilities which have to be borne by the utilities. Today's increasing utility involvement in the nuclear fuel management is shown, as well as future fuel management trends. The fuel management activities of the utilities are analysed with respect to organizational, technical, safeguarding, and financial aspects. The active participation of the utilities in fuel management helps to achieve high availability and flexibility of the nuclear power plant during its whole life as well as safe waste isolation. This can be ensured by continuous optimization of all fuel management aspects of the power plant or, on a larger scale, of a power plant system, i.e. activities by utilities to minimize fuel-cycle effects on the environment, which include optimization of fuel behaviour, and radiation exposure to the public and personnel; and technical and economic evaluations by utilities of out- and in-core fuel management. (author)

  3. PNRA Process for Utilizing Experience Feedback for Enhancing Nuclear Safety

    International Nuclear Information System (INIS)

    Shah, Z.H.

    2016-01-01

    One of the elements essential for any organization to become a learning organization is to learn from its own and others experience. The importance of utilizing experience feedback for enhancing operational safety is highlighted in nuclear industry again and again and this has resulted in establishment of several national and international forums. In addition, IAEA action plan on nuclear safety issued after Fukushima accident further highlighted the importance of experience sharing among nuclear community to enhance global nuclear safety regime. PNRA utilizes operating experience feedback gathered through different sources in order to improve its regulatory processes. During the review of licensing submissions, special emphasis is given to utilize the lessons learnt from experience feedback relating to nuclear industry within and outside the country. This emphasis has gradually resulted in various safety improvements in the facilities and processes. Accordingly, PNRA has developed a systematic process of evaluation of international operating experience feedback with the aim to create safety conscious approach. This process includes collecting information from different international forums such as IAEA, regulatory bodies of other countries and useful feedback of past accidents followed by its screening, evaluation and suggesting recommendations both for PNRA and its licensees. As a result of this process, several improvements concerning regulatory inspection plans of PNRA as well as in regulatory decision making and operational practices of licensees have been highlighted. This paper will present PNRA approach for utilizing experience feedback in its regulatory processes for enhancing / improving nuclear safety. (author)

  4. Nuclear utility self-assessment as viewed by the corporate nuclear safety committee

    International Nuclear Information System (INIS)

    Corcoran, W.R.

    1992-01-01

    This paper discusses how corporate nuclear safety committees use the principles of self-assessment to enhance nuclear power plant safety performance. Corporate nuclear safety committees function to advise the senior nuclear power executive on matters affecting nuclear safety. These committees are required by the administrative controls section of the plant technical specifications which are part of the final safety analysis report and the operating license. Committee membership includes senior utility executives, executives from sister utilities, utility senior technical experts, and outside consultants. Current corporate nuclear safety committees often have a finely tuned intuitive feel for self-assessment that they use to probe the underlying opportunities for quality and safety enhancements. The questions prompted by the self-assessment orientation enable the utility line organization members to gain better perspectives on the characteristics of the organizational systems that they manage and work in

  5. EPRI expert system activities for nuclear utility industry application

    International Nuclear Information System (INIS)

    Naser, J.A.

    1990-01-01

    This paper reports on expert systems which have reached a level of maturity where they offer considerable benefits for the nuclear utility industry. The ability of expert systems to enhance expertise makes them an important tool for the nuclear utility industry in the areas of engineering, operations and maintenance. Benefits of expert system applications include comprehensive and consistent reasoning, reduction of time required for activities, retention of human expertise and ability to utilize multiple experts knowledge for an activity. The Electric Power Research Institute (EPRI) has been performing four basic activities to help the nuclear industry take advantage of this expert system technology. The first is the development of expert system building tools which are tailored to nuclear utility industry applications. The second is the development of expert system applications. The third is work in developing a methodology for verification and validation of expert systems. The last is technology transfer activities to help the nuclear utility industry benefit from expert systems. The purpose of this paper is to describe the EPRI activities

  6. Development of integrated nuclear data utilization system for innovative reactors

    International Nuclear Information System (INIS)

    Naoki, Yamano; Masayuki, Igashira; Akira, Hasegawa; Kiyoshi, Kato

    2005-01-01

    An integrated nuclear data utilization system has been developing for innovative nuclear energy systems such as innovative reactors and accelerator-driven systems. The system has been constructed as a modular code system, which consists of a managing system and two subsystems. The management system named CONDUCT controls system resource management of the PC Linux server and the user authentication through Internet access. A subsystem is the nuclear data search and plotting subsystem based on a SPES engine developed by Hokkaido University. Nuclear data such as EXFOR, JENDL-3.3, ENDF/B-VI and JEFF-3.1 can be searched and plotted in the subsystem. The other is the nuclear data processing and utilization subsystem, which is able to handle JENDL-3.3, ENDF/B-VI and JEFF-3.1 to generate point-wise and group cross sections in several formats, and perform various criticality and shielding benchmarks for verification of nuclear data and validation of design methods for innovative reactors. This paper presents an overview of the integrated nuclear data utilization system, describes the progress of the system development to examine the operability of the user interface and discuss specifications of the two subsystems. (authors)

  7. Concepts for reducing nuclear utility inventory carrying costs

    International Nuclear Information System (INIS)

    Graybill, R.E.; DiCola, F.E.; Solanas, C.H.

    1985-01-01

    Nuclear utilities are under pressure to reduce their operating and maintenance expenses such that the total cost of generating electricity through nuclear power remains an economically attractive option. One area in which expenses may be reduced is total inventory carrying cost. The total inventory carrying cost consists of financing an inventory, managing the inventory, assuring quality, engineering of acceptable parts specifications, and procuring initial and replenishment stock. Concepts and methodology must be developed to reduce the remaining expenses of a utility's total inventory carrying cost. Currently, two concepts exist: pooled inventory management system (PIMS), originally established by General Electric Company and a group of boiling water reactor owners, and Nuclear Parts Associates' (NUPA) shared inventory management program (SIMP). Both concepts share or pool parts and components among utilities. The SIMP program objectives and technical activities are summarized

  8. Nuclear fuel utilization at the Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

    Boyadzhiev, Z [Kombinat Atomna Energetika, Kozloduj (Bulgaria); Kharalampieva, Ts; Pejchinov, Ts

    1996-12-31

    Data on core loading and operation conditions during past fuel cycles of the Units 1 to 6 at the Kozloduy NPP are presented. The Units 1 and 2 have reached average discharge fuel burn-up of 31 MW d/kg U, the Unit 3 - 34 MW d/kg U and the Unit 4 - 36.5 MW d/kg U. By use of dummies and low-leakage core loading patterns for WWER-440 cores an effective reduction in reactor pressure vessel irradiation is obtained. By increasing the enrichment level and improving the characteristics of the Units 3 and 4, a design fuel cycles duration has been reduced by 5-10% in number of assemblies. Core loading design has been modelled using computer codes SPPS-1, BIPR-7, ALBOM, PROROC. A 3-year fuel cycle utilizing 4.4% enriched fuel proved to be more efficient for WWER-1000 by 15% reduction in fuel cost compared to the 2-year cycle. Future developments include improvements of the in-core monitoring system and process on-line simulation based on more accurate computer codes. 7 refs., 6 figs., 10 tabs.

  9. Nuclear power plant waste heat utilization

    Energy Technology Data Exchange (ETDEWEB)

    Ryther, J.H.; Huke, R.E.; Archer, J.C.; Price, D.R.; Jewell, W.J.; Hayes, T.D.; Witherby, H.R.

    1977-09-01

    The possibility of using Vermont Yankee condenser effluent for commercial food growth enhancement was examined. It was concluded that for the Vermont Yankee Nuclear Station, commercial success, both for horticulture and aquaculture endeavors, could not be assured without additional research in both areas. This is due primarily to two problems. First, the particularly low heat quality of our condenser discharge, being nominally 72 +- 2/sup 0/F; and second, to the capital intensive support systems. The capital needed for the support systems include costs of pumps, piping and controls to move the heated water to growing facilities and the costs of large, efficient heat exchangers that may be necessary to avoid regulatory difficulties due to the 1958 Delaney Amendment to the U.S. Food, Drug and Cosmetics Act. Recommendations for further work include construction of a permanent aquaculture research laboratory and a test greenhouse complex based on a greenhouse wherein a variety of heating configurations would be installed and tested. One greenhouse would be heated with biogas from an adjacent anaerobic digester thermally boosted during winter months by Vermont Yankee condenser effluent. The aquaculture laboratory would initially be dedicated to the Atlantic salmon restoration program. It appears possible to raise fingerling salmon to smolt size within 7 months using water warmed to about 60/sup 0/F. The growth rate by this technique is increased by a factor of 2 to 3. A system concept has been developed which includes an aqua-laboratory, producing 25,000 salmon smolt annually, a 4-unit greenhouse test horticulture complex and an 18,000 square foot commercial fish-rearing facility producing 100,000 pounds of wet fish (brook trout) per year. The aqualab and horticulture test complex would form the initial phase of construction. The trout-rearing facility would be delayed pending results of laboratory studies confirming its commercial viability.

  10. Nuclear power plant waste heat utilization

    International Nuclear Information System (INIS)

    Ryther, J.H.; Huke, R.E.; Archer, J.C.; Price, D.R.; Jewell, W.J.; Hayes, T.D.; Witherby, H.R.

    1977-09-01

    The possibility of using Vermont Yankee condenser effluent for commercial food growth enhancement was examined. It was concluded that for the Vermont Yankee Nuclear Station, commercial success, both for horticulture and aquaculture endeavors, could not be assured without additional research in both areas. This is due primarily to two problems. First, the particularly low heat quality of our condenser discharge, being nominally 72 +- 2 0 F; and second, to the capital intensive support systems. The capital needed for the support systems include costs of pumps, piping and controls to move the heated water to growing facilities and the costs of large, efficient heat exchangers that may be necessary to avoid regulatory difficulties due to the 1958 Delaney Amendment to the U.S. Food, Drug and Cosmetics Act. Recommendations for further work include construction of a permanent aquaculture research laboratory and a test greenhouse complex based on a greenhouse wherein a variety of heating configurations would be installed and tested. One greenhouse would be heated with biogas from an adjacent anaerobic digester thermally boosted during winter months by Vermont Yankee condenser effluent. The aquaculture laboratory would initially be dedicated to the Atlantic salmon restoration program. It appears possible to raise fingerling salmon to smolt size within 7 months using water warmed to about 60 0 F. The growth rate by this technique is increased by a factor of 2 to 3. A system concept has been developed which includes an aqua-laboratory, producing 25,000 salmon smolt annually, a 4-unit greenhouse test horticulture complex and an 18,000 square foot commercial fish-rearing facility producing 100,000 pounds of wet fish (brook trout) per year. The aqualab and horticulture test complex would form the initial phase of construction. The trout-rearing facility would be delayed pending results of laboratory studies confirming its commercial viability

  11. Study of factors governing US utility nuclear power decisions

    International Nuclear Information System (INIS)

    1980-05-01

    Under DOE contract No. DE-AC02-79ET34009, The S.M. Stoller Corporation has conducted a study of US utility attitudes toward nuclear power. In the course of this study SMSC carried out a utility survey the objectives of which were: (1) to identify and rank in importance the governing considerations in actions taken in the past three years to cancel or defer nuclear projects, and (2) to gain insight into the circumstances and attitudes likely to govern new base-load commitments over the next several years. During the survey, contacts were made at the senior management level with utilities representing approximately half of the country's total electric capacity and two-thirds of its present nuclear commitment. Analysis of the responses led to the conclusion that most, if not all, of the decisions reached by the respondent utilities in the past several years to cancel or defer nuclear projects were triggered by one or a combination of the following four considerations: financial constraints; reduction in expected system load growth; schedule delay in licensing and construction and/or unpredictability; and adverse state government policies or attitudes regarding nuclear power

  12. Absolute concentration determination of phosphorus metabolites in the Langendorff-perfused rabbit heart by phosphorus-31 nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Gard, J.K.

    1984-01-01

    The concentrations of mobile high energy phosphorus metabolites and intracellular pH of Langendorff-perfused rabbit heart have been determined under control and reduced flow conditions. Absolute concentration determination was accomplished by Lorentzian lineshape analysis after development of hexachlorocyclotriphosphazene as an external intensity standard. Hearts were demonstrated to be biochemically and physiologically competent during control perfusion periods and compromised during reduced flow conditions by independent hemodynamic and metabolic measurements coincident with the NMR experiment. Reduction in perfusate flow from 20 mL/min to 5.0 mL/min (25% flow) or 2.5 mL/min (12.5% flow) demonstrated a fall in phosphocreatine and adenosine triphosphate concentrations, a rise in cytosolic inorganic phosphate concentrations, and drops in pH. Subsequent recovery upon reflow was observed. The derived values for the free concentration of ADP were very close to the reported values of the Michaelis constant for respiratory stimulation, implicating a regulatory role for this molecule in cellular respiration. Strong evidence that the creating kinase reaction was in equilibrium in the 25% flow study was seen. The NMR observable correlated closely with myocardial performance and biochemical indices of metabolic function, and supported the use of phosphocreatine as an indicator of current metabolic integrity

  13. Report of nuclear utility industry responses to Kemeny Commission recommendations

    International Nuclear Information System (INIS)

    1989-02-01

    The purpose of this paper is to provide a report of nuclear utility industry progress in responding to the recommendations of the President's Commission on the Accident at Three Mile Island (The Kemeny Commission). On April 11, 1979, in response to TMI, President Carter established a Commission to conduct '.... a comprehensive study and investigation of the recent accident involving the nuclear power facility on Three Mile Island in Pennsylvania'. The Commission was chaired by Dr. John G. Kemeny, then President of Dartmouth College. (A list of all members of The Kemeny Commission is provided in Attachment to the Appendix ). The report of the commission's findings and recommendations was transmitted to the President in October 1979. During this same period, the nuclear utility industry responded to TMI by creating the Institute of Nuclear Power Operations (INPO) with a mission to promote the highest levels of safety and reliability - to promote excellence - in the operation of nuclear electric generating plants. In addition, the Nuclear Safety Analysis Center (NSAC) was established at the Electric Power Research Institute (EPRI to evaluate the accident and assist in determining the best industry response. In a White House paper (and press release) of December 7 1979, the President announced that he agreed fully with the spirit and intent of al the Kemeny Commission recommendations and requested that the industry and The Nuclear Regulatory Commission (NRC) comply with the recommendations. The President also recognized the industry initiative in establishing INPO and called for several actions involving the Institute; the President directed the Department of Energy and other government agencies to provide assistance to INPO and the industry. An overall status of the nuclear utility industry responses to Kemeny Commission recommendations in the key areas directly related to nuclear plant operations is provided below. A more detailed status of industry responses to the

  14. Report of nuclear utility industry responses to Kemeny Commission recommendations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-02-15

    The purpose of this paper is to provide a report of nuclear utility industry progress in responding to the recommendations of the President's Commission on the Accident at Three Mile Island (The Kemeny Commission). On April 11, 1979, in response to TMI, President Carter established a Commission to conduct '.... a comprehensive study and investigation of the recent accident involving the nuclear power facility on Three Mile Island in Pennsylvania'. The Commission was chaired by Dr. John G. Kemeny, then President of Dartmouth College. (A list of all members of The Kemeny Commission is provided in Attachment to the Appendix ). The report of the commission's findings and recommendations was transmitted to the President in October 1979. During this same period, the nuclear utility industry responded to TMI by creating the Institute of Nuclear Power Operations (INPO) with a mission to promote the highest levels of safety and reliability - to promote excellence - in the operation of nuclear electric generating plants. In addition, the Nuclear Safety Analysis Center (NSAC) was established at the Electric Power Research Institute (EPRI to evaluate the accident and assist in determining the best industry response. In a White House paper (and press release) of December 7 1979, the President announced that he agreed fully with the spirit and intent of al the Kemeny Commission recommendations and requested that the industry and The Nuclear Regulatory Commission (NRC) comply with the recommendations. The President also recognized the industry initiative in establishing INPO and called for several actions involving the Institute; the President directed the Department of Energy and other government agencies to provide assistance to INPO and the industry. An overall status of the nuclear utility industry responses to Kemeny Commission recommendations in the key areas directly related to nuclear plant operations is provided below. A more detailed status of industry responses to the

  15. A utility's perspective on the Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    Berry, W.W.

    1985-01-01

    The Nuclear Waste Policy Act is especially important to utilities because their customers pay for the disposal program, and the program is vital to nuclear operations and reconsideration of the nuclear option. DOE's accomplishments in implementing the Act are noteworthy, but we are concerned that some of them have been achieved later than specified by the schedule in the Act. We make recommendations regarding disposal fees, defense wastes, and shipping casks. Virginia Power has adopted a three-part strategy relying mainly on developing dry cask storage to solve the company's interim storage problems

  16. EPRI Guide to Managing Nuclear Utility Protective Clothing Programs

    International Nuclear Information System (INIS)

    Kelly, J.J.; Kelly, D.M.

    1993-10-01

    The Electric Power Research Institute (EPRI) commissioned a radioactive waste related project (RP2414-34) in 1989 to produce a guide for developing and managing nuclear plant protective clothing programs. Every nuclear facility must coordinate some type of protective clothing program for its radiation workers to ensure proper and safe protection for the wearer and to maintain control over the spread of contamination. Yet, every nuclear facility has developed its own unique program for managing such clothing. Accordingly, a need existed for a reference guide to assist with standardizing protective clothing programs and in controlling the potentially escalating economics of such programs. The initial Guide to Managing Nuclear Utility Protective Clothing Programs, NP-7309, was published in May 1991. Since that time, a number of utilities have reviewed and/or used the report to enhance their protective clothing programs. Some of these utilities requested that a computer program be developed to assist utilities in evaluating the economics of protective clothing programs consistent with the guidance in NP-7309. The PCEVAL computer code responds to that industry need. This report, the PCEVAL User's Manual, provides detailed instruction on use of the software

  17. Improved biomass utilization through the use of nuclear techniques

    International Nuclear Information System (INIS)

    1988-10-01

    Biomass is a major by-product resource of agriculture and food manufacturing, but it is under-utilized as a source of food, fibre, and chemicals. Nuclear techniques provide unique tools for studies of the capabilities of micro-organisms in methane digestor operation and in the transformation of lignocellulosic materials to useful products. Nuclear techniques have also been effectively employed as mutagenic agents in the preparation of more efficient microbial strains for the conversion of biomass. This report reviews the variety and diversity of such applications with focus on the development of microbial processes to utilize agricultural wastes and by-products. The value of nuclear techniques is manifestly demonstrated in the production of efficient microbial mutant strains, in the tracing of metabolic pathways, in the monitoring of lignin degradation and also of fermenter operation. Refs, figs and tabs

  18. Developing engineering analysis capabilities at a nuclear utility

    International Nuclear Information System (INIS)

    Miller, J.S.

    1992-01-01

    When a nuclear plant is originally designed and constructed, a large staff of analytical and design personnel is used by the architectural and engineering (A/E) firm(s) and the nuclear steam supply system (NSSS) engineering firm(s) to provide the technical specifications needed for the plant to function and satisfy US Nuclear Regulatory Commission (NRC) requirements. During this design process, thousands of calculations are performed, some using large sophisticated computer programs. Once the plant is operational, the utility assumes the large responsibility for plant design. Utility personnel must understand the fundamentals of operating the plant, the technical information in the updated safety analysis report, all calculations used to design the plant, and the input for all design specification documents. Without this knowledge, utility personnel cannot successfully perform modifications or new analyses required by the NRC, such as probabilistic risk assessment (PRA) and motor-operated valve programs, and maintain the safe and reliable operation of the plant. Therefore, it is very important to have on-site personnel who understand how the calculations are performed and used in the design basis. This paper discusses the organization of the engineering analysis group, which provides technical support for River Bend Station (RBS) of Gulf States Utilities

  19. Utilizations of filtered neutron beams at Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    Hien, P.D.; Chau, L.N.; Tan, V.H.; Hiep, N.T.; Phuong, L.B.

    1992-01-01

    Neutron beam utilizations in basic and applied researches have been important activities at the Dalat nuclear reactor. The neutron filters with single crystal of silicon are used to produce thermal neutrons at the tangential horizontal channel and quasi-monoenergetic 144 KeV and 54 KeV neutrons at the piercing beam tube. The paper presents some relevant characteristics of the filtered neutron beams at the two horizontal channels. Applications of neutron beams in prompt gamma-ray activation analysis and in nuclear data measurements are briefly described. (author)

  20. Utility says grid firm owes money for nuclear

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Russian nuclear power stations are owed more than 100 billion rubles, according to Yevgeniy Ignatenko, vice president of the state-owned utility organization Rosenergoatom, which is responsible for operation of nuclear power stations. A Russian grid company, which came into existence at the beginning of 1993, is supposed to collect money from consumers and pay the power stations for the electricity that they have supplied, but Ignatenko complains that this company has paid less than half of the money it owes for the first eight months of the year

  1. Utilization of solar and nuclear energy for hydrogen production

    International Nuclear Information System (INIS)

    Fischer, M.

    1987-01-01

    Although the world-wide energy supply situation appears to have eased at present, non-fossil primary energy sources and hydrogen as a secondary energy carrier will have to take over a long-term and increasing portion of the energy supply system. The only non-fossil energy sources which are available in relevant quantities, are nuclear energy, solar energy and hydropower. The potential of H 2 for the extensive utilization of solar energy is of particular importance. Status, progress and development potential of the electrolytic H 2 production with photovoltaic generators, solar-thermal power plants and nuclear power plants are studied and discussed. The joint German-Saudi Arabian Research, Development and Demonstration Program HYSOLAR for the solar hydrogen production and utilization is summarized. (orig.)

  2. Nuclear fuel financing by USA investor-owned utilities

    International Nuclear Information System (INIS)

    Cave, W.F.

    1981-01-01

    Investor-owned utilities in the USA currently have almost 60 nuclear plants in commercial operation and an additional 90 plants under construction or awaiting operating licenses. To understand the specific techniques implemented to finance nuclear fuel and the advantages which they provide to individual companies, the total financing needs of the industry, the traditional pattern which utility external financing has taken, and the varied financial and regulatory bodies whose often conflicting objectives management must attempt to reconcile, must be understood. The aim of this paper is to aid such an understanding. The subject is discussed under the following headings: industry background; regulation and rating agencies; management objectives; financing structure; advantages (low financing cost; regulatory treatment; freer nature of agreement; access to commercial paper market; appropriate financing time-span; rating benefits; accounting treatment); conclusions. (U.K.)

  3. Safety study on nuclear heat utilization system - accident delineation and assessment on nuclear steelmaking pilot plant

    International Nuclear Information System (INIS)

    Yoshida, T.; Mizuno, M.; Tsuruoka, K.

    1982-01-01

    This paper presents accident delineation and assessment on a nuclear steelmaking pilot plant as an example of nuclear heat utilization systems. The reactor thermal energy from VHTR is transported to externally located chemical process plant employing helium-heated steam reformer by an intermediate heat transport loop. This paper on the nuclear steelmaking pilot plant will describe (1) system transients under accident conditions, (2) impact of explosion and fire on the nuclear reactor and the public and (3) radiation exposure on the public. The results presented in this paper will contribute considerably to understanding safety features of nuclear heat utilization system that employs the intermediate heat transport loop and the helium-heated steam reformer

  4. Initiatives in training program evaluation outside the nuclear utility industry

    International Nuclear Information System (INIS)

    Allen, C.J.

    1987-01-01

    Training literature is reviewed, and program evaluative practices outside the nuclear utility industry are reported. The findings indicate some innovations in philosophy and practice and program evaluation, although not necessarily in the context of evaluation as a route to assessing the impact of training. Program evaluation is described in the context of the impact of training, suggesting continued efforts to accept a multivariate concept of individual and organizational performance

  5. Utilization of atomic energy in Asia and nuclear nonproliferation system

    International Nuclear Information System (INIS)

    Ishii, Makoto

    1995-01-01

    The economical growth in East Asia is conspicuous as it was called East Asian Miracle, and also the demand of energy increased rapidly. The end of Cold War created the condition for the further development in this district. Many countries advanced positively the plan of atomic energy utilization, and it can be said that the smooth progress of atomic energy utilization is the key for the continuous growth in this district in view of the restriction of petroleum resources and its price rise in future and the deterioration of global environment. The nuclear nonproliferation treaty (NPT) has accomplished large role, but also its limitation became clear. At present, there is not the local security system in Asia, but in order that the various countries in Asia make the utilization of atomic energy and the security compatible, it is useful to jointly develop safety technology, execute security measures and form the nuclear fuel cycle as Asia. Energy and environmental problems in Asia are reported. Threat is essentially intention and capability, and the regulation only by capability regardless of intention brings about unrealistic result. The limitation of the NPT is discussed. The international relation of interdependence deepends after Cold War, and the security in Asia after Cold War is considered. As the mechanism of forming the nuclear fuel cycle for whole Asia, it is desirable to realize ASIATOM by accumulating the results of possible cooperation. (K.I.)

  6. Parametric utility comparison of coal and nuclear electricity generation

    International Nuclear Information System (INIS)

    Maurer, K.M.

    1977-02-01

    The advantages and limitations of an explicit quantitative model for decision making are discussed. Several different quantitative models are presented, noting that the use of an expected utility maximization decision rule allows both the direct incorporation of multidimensional descriptions of the possible outcomes, and considerations of risk averse behavior. A broad class of utility functions, characterized by linear risk tolerance, was considered and extended to a multidimensional form. Choosing a multivariate risk neutral extension, using constant absolute risk aversion utility functions for monetary effects and for increased mortality, the author indicated how the parameters of this utility function can be selected to represent the decision maker's preferences, and suggest a reasonable range of values for the parameters. After describing an illustrative set of data on the risks inherent in coal burning and nuclear electricity generation facilities, the author used the chosen utility model to compare the overall risks associated with each technology, observing the effect of variations in the utility parameters and in the risk distributions on the implied preferences

  7. $35 billion habit: will nuclear cost overruns bankrupt the utilities

    International Nuclear Information System (INIS)

    Morgan, R.E.

    1980-01-01

    The Nuclear Regulatory Commission (NRC) has proposed some 150 modifications in the design and operation of nuclear power plants as a result of the accident at Three Mile Island. The Atomic Industrial Forum estimates the total cost of the NRC's proposed rule changes at $35.5 billion ($3.5 billion in capital costs for the entire industry, and $32 billion in outage and construction-delay costs to the utilities) for existing facilities and for those with construction well underway. The changes range from improved training for reactor workers to a major overhaul of the reactor-containment design. The nuclear industry is asking the NRC to modify the proposals citing excessive costs (like the $100 million changes needed for a plant that cost $17 million to build) and safety (some of the complex regulations may interfere with safety). Financing the changes has become a major problem for the utilities. If the regulators allow all the costs to be passed along to the consumer, the author feels electricity will be too expensive for the consumer

  8. HTTR demonstration test plan for industrial utilization of nuclear heat

    International Nuclear Information System (INIS)

    Sato, Hiroyuki; Ohashi, Hirofumi; Yan, Xing L.; Kubo, Shinji; Nishihara, Tetsuo; Tachibana, Yukio; Inagaki, Yoshiyuki

    2014-09-01

    Japan Atomic Energy Agency has been conducting research and development with a central focus on the utilization of High Temperature engineering Test Reactor (HTTR), the first High Temperature Gas-cooled Reactor (HTGR) in Japan, towards the realization of industrial use of nuclear heat. Several studies have made on the integration of the HTTR with thermochemical iodine-sulfur process and steam methane reforming hydrogen production plant (H 2 plant) as well as helium gas turbine power conversion system. In addition, safety standards for coupling a H 2 plant to a nuclear facility has been investigated. Based on the past design information, the present study identified test items to be validated in the HTTR demonstration test to accomplish a formulation of safety requirement and design consideration for coupling a H 2 plant to a nuclear facility as well as confirmation of overall performance of helium gas turbine system. In addition, plant concepts for the heat utilization system to be connected with the HTTR are investigated. (author)

  9. Plant life management optimized utilization of existing nuclear power plants

    International Nuclear Information System (INIS)

    Watzinger, H.; Erve, M.

    1999-01-01

    For safe, reliable and economical nuclear power generation it is of central importance to understand, analyze and manage aging-related phenomena and to apply this information in the systematic utilization and as-necessary extension of the service life of components and systems. An operator's overall approach to aging and plant life management which also improves performance characteristics can help to optimize plant operating economy. In view of the deregulation of the power generation industry with its increased competition, nuclear power plants must today also increasingly provide for or maintain a high level of plant availability and low power generating costs. This is a difficult challenge even for the newest, most modern plants, and as plants age they can only remain competitive if a plant operator adopts a strategic approach which takes into account the various aging-related effects on a plant-wide basis. The significance of aging and plant life management for nuclear power plants becomes apparent when looking at their age: By the year 2000 roughly fifty of the world's 434 commercial nuclear power plants will have been in operation for thirty years or more. According to the International Atomic Energy Agency, as many as 110 plants will have reached the thirty-year service mark by the year 2005. In many countries human society does not push the construction of new nuclear power plants and presumably will not change mind within the next ten years. New construction licenses cannot be expected so that for economical and ecological reasons existing plants have to be operated unchallengeably. On the other hand the deregulation of the power production market is asking just now for analysis of plant life time to operate the plants at a high technical and economical level until new nuclear power plants can be licensed and constructed. (author)

  10. Peaceful utilization of nuclear energy in the FRG

    International Nuclear Information System (INIS)

    1980-01-01

    The present paper gives a summary of the initiatives taken by the Deutscher Bundestag (Federal Assembly) for peaceful utilization of nuclear energy consideration of relevant secondary aspects like area planning, assessment of technology consequences, the introduction of the Verbandsklage (write of associations to enter in public proceedings) etc. It is an extended table of contents of the 7th and 8th election period. Fixed days was the 1rst of Jan, 1980. Apart from this temporary limitation, only the Enquete-Commission's report Future Nuclear Energy Policy was taken into consideration because in this report the discussion about energy policy of the last two election periods is brought to an end. (orig.) [de

  11. National need for utilizing nuclear energy for process heat generation

    International Nuclear Information System (INIS)

    Gambill, W.R.; Kasten, P.R.

    1984-01-01

    Nuclear reactors are potential sources for generating process heat, and their applications for such use economically competitive. They help satisfy national needs by helping conserve and extend oil and natural gas resources, thus reducing energy imports and easing future international energy concerns. Several reactor types can be utilized for generating nuclear process heat; those considered here are light water reactors (LWRs), heavy water reactors (HWRs), gas-cooled reactors (GCRs), and liquid metal reactors (LMRs). LWRs and HWRs can generate process heat up to 280 0 C, LMRs up to 540 0 C, and GCRs up to 950 0 C. Based on the studies considered here, the estimated process heat markets and the associated energy markets which would be supplied by the various reactor types are summarized

  12. Utilization of waste heat from nuclear power plants in agriculture

    International Nuclear Information System (INIS)

    Horacek, P.

    1981-01-01

    The development of nuclear power will result in the relative and absolute increase in the amount of waste heat which can be used in agriculture for heating greenhouses, open spaces, for fish breeding in heated water, for growing edible mushrooms, growing algae, for frost protection of orchards, air conditioning of buildings for breeding livestock and poultry, and for other purposes. In addition of the positive effect of waste heat, the danger increases of disease, weeds and pests. Pilot plant installations should be build in Czechoslovakia for testing the development of waste heat utilization. (Ha)

  13. Illustrative comparison of one utility's coal and nuclear choices

    International Nuclear Information System (INIS)

    Keeney, R.L.; Sicherman, A.

    1983-01-01

    The technology choices facing an individual utility are complex decision problems. The paper illustrates a method designed to assist an individual utility company in making the choices in a logically consisnt manner. The resulting evaluation model, based on the principles of decision analysis, explicitly addresses the complexity to provide a basis for decision making and support for defending the decision before reviewers. The model, which incorporates economic, environmental, social, safety, and regulatory effects, is demonstrated using a coal/nuclear choice which may be faced by Utah Power and Light Company in the near future. This analysis is meant to be illustrative; more effort would be needed to gather information to support a policy decision

  14. Advanced ceramics for nuclear heat utilization and energy harvesting

    International Nuclear Information System (INIS)

    Prakash, Deep; Purohit, R.D.; Sinha, P.K.

    2015-01-01

    In recent years concerns related to global warming and green house gas emissions have focused the attention towards lowering the carbon foot print of energy generation. In this scenario, nuclear energy is considered as one of the strongest options to take on the challenges. Further, the nuclear heat, originated from the fission of nuclear fuels may be utilized not only by conversion to electricity using conventional techniques, but also may be used for production of hydrogen by splitting water. In the endeavor of realizing sustainable energy generation technologies, ceramic materials find key role as critical components. This paper covers an overview of various ceramic materials which are potential candidates for energy and hydrogen generation devices. These include solid oxide fuel cells, thermoelectric oxides and sodium conducting beta-alumina for alkali metal thermoelectric converters (AMTEC). The materials, which are generally complex oxides often need to be synthesized using chemical methods for purity and compositional control. Further, ceramic materials offer advantages in terms of doping different cations to engineer defects and maneuver properties. Nonetheless, shaping of ceramics to complex components is a challenging task, due to which various techniques such as isopressing, tape-casting, extrusion, slurry coating, spray deposition etc. are employed. The paper also provides a highlight of fabrication techniques and demonstration of miniature devices which are at various stages of development. (author)

  15. Coping with nuclear power risks: the electric utility incentives

    International Nuclear Information System (INIS)

    Starr, C.; Whipple, C.

    1982-01-01

    The financial risks associated with nuclear power accidents are estimated by interpolating between frequency-vs.-severity data from routine outages and the frequency-vs.-severity estimates from the Nuclear Regulatory Commission's (NRC's) Reactor Safety Study (WASH-1400). This analysis indicates that the expected costs of plant damage and lost power production are large compared to the public risks estimated in WASH-1400, using values from An Approach to Quantitative Safety Goals for Nuclear Power Plants (NUREG-0739), prepared by the NRC Advisory Committee on Reactor Safeguards. Analyses of the cost-effectiveness of accident-prevention investments that include only anticipated public safety benefits will underestimate the value of such investments if reductions in power plant damage risk are not included. The analysis also suggests that utility self-interest and the public interest in safety are generally coincident. It is argued that greater use could be made of this self-interest in regulation if the relationship between the NRC and the industry were more cooperative, less adversary in nature

  16. Basic plans of nuclear energy development and utilization for fiscal 1982 (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Prime Minister, concerning the basic plans of nuclear energy development and utilization for fiscal 1982, was presented; the NSC has decided on the plans drawn up by the Prime Minister. Nuclear power generation as the nucleus of petroleum substitutes must be developed steadily. For the purpose, nuclear fuel cycle should be established, including the securing of uranium resources, uranium enrichment, fuel reprocessing, and waste management. The contents are as follows: the strengthening of nuclear safety measures, the promotion of nuclear power generation, the establishment of nuclear fuel cycle, the development of advanced types of reactors, the research on nuclear fusion, the research and development of nuclear powered ships, the promotion of radiation utilization, the strengthening of basis for nuclear energy development and utilization, the promotion of international cooperation, the strengthening of safeguard and nuclear material protection measures, fiscal 1982 budgets related to nuclear energy. (Mori, K.)

  17. Compiling Utility Requirements For New Nuclear Power Plant Project

    International Nuclear Information System (INIS)

    Patrakka, Eero

    2002-01-01

    Teollisuuden Voima Oy (TVO) submitted in November 2000 to the Finnish Government an application for a Decision-in-Principle concerning the construction of a new nuclear power plant in Finland. The actual investment decision can be made first after a positive decision has been made by the Government and the Parliament. Parallel to the licensing process, technical preparedness has been upheld so that the procurement process can be commenced without delay, when needed. This includes the definition of requirements for the plant and preliminary preparation of bid inquiry specifications. The core of the technical requirements corresponds to the specifications presented in the European Utility Requirement (EUR) document, compiled by major European electricity producers. Quite naturally, an amount of modifications to the EUR document are needed that take into account the country- and site-specific conditions as well as the experiences gained in the operation of the existing NPP units. Along with the EUR-related requirements concerning the nuclear island and power generation plant, requirements are specified for scope of supply as well as for a variety of issues related to project implementation. (author)

  18. Utility survey on nuclear power plant siting and nuclear energy centers

    International Nuclear Information System (INIS)

    Cope, D.F.; Bauman, H.F.

    1977-01-01

    Most of the large U.S. utilities were surveyed by telephone and mail on questions concerning nuclear power plant siting and nuclear energy centers (NECs). The main purpose of the survey was for guidance of ERDA's NEC program. The questions covered the following topics: availability of sites; impact of environmental and other restraints; plans for development of multi-unit sites; interest in NEC development; interest in including fuel-cycle facilities in NECs; and opinions on the roles desired for the state and Federal governments in power plant siting. The main conclusion of the survey was that, while many utilities were considering multiple-unit sites of 2 to 5 units, none were planning larger energy centers at the present time. However, several expressed interest in NECs as a long-range future development

  19. Service to the Electric Utility Industry by the Ford Nuclear Reactor, University of Michigan

    International Nuclear Information System (INIS)

    Burn, R.R.; Simpson, P.A.; Cook, G.M.

    1993-01-01

    Since 1977, the staff of the University of Michigan's Ford Nuclear Reactor has been providing irradiation, testing, analytical, and training services to electric utilities and to suppliers of the nuclear electric utility industry. This paper discusses the reactor's irradiation facilities; reactor programs and utilization; materials testing programs; neutron activation analysis activities; and training programs conducted

  20. Factors affecting nuclear research reactor utilization across countries

    International Nuclear Information System (INIS)

    Hien, P.D.

    2000-01-01

    In view of the worldwide declining trend of research reactor utilization and the fact that many reactors in developing countries are under-utilised, a question naturally arises as to whether the investment in a research reactor is justifiable. Statistical analyses were applied to reveal relationships between the status of reactor utilization and socio-economic conditions among countries, that may provide a guidance for reactor planning and cost benefit assessment. The reactor power has significant regression relationships with size indicators such as GNP, electricity consumption and R and D expenditure. Concerning the effectiveness of investment in research reactors, the number of reactor operation days per year only weakly correlates with electricity consumption and R and D expenditure, implying that there are controlling factors specific of each group of countries. In the case of less developed countries, the low customer demands on reactor operation may be associated with the failure in achieving quality assurance for the reactor products and services, inadequate investment in the infrastructure for reactor exploitation, the shortage of R and D funding and well trained manpower and the lack of measures to get the scientific community involved in the application of nuclear techniques. (author)

  1. An operating nuclear utility's experience with the ALARA design of a new nuclear unit

    International Nuclear Information System (INIS)

    Rodgers, R.C.

    1985-01-01

    This talk presents a review of how operating experience at Northeast Utilities has been factored into the design of a new nuclear unit and the development and management of the radiation protection program. Their operational experience has indicated that there are two facets to keeping radiation exposures ALARA. The first is the proper ALARA design of the unit. The other facet is the design of a comprehensive radiation protection program. The author discusses these facets in some detail

  2. On the state of the art and some trends in industrial utilization of nuclear power

    International Nuclear Information System (INIS)

    Rockstroh, R.

    1980-01-01

    The status achieved in nuclear power utilization in the world and the prospects of further development are presented. Concerning the technological maturity as well as the economy and the environmental aspects the experience hitherto obtained enables the conclusion that nuclear plants have not to fear any comparison with conventional power stations. The social difficulties in the industrially developed capitalist countries in managing the complex problems of utilizing nuclear power are described and commented. Some political aspects of further nuclear power development are also indicated. Information is given about the measures and some objectives for acceleration of nuclear power utilization in the CMEA member states. (author)

  3. Overview of reductants utilized in nuclear fuel reprocessing/recycling

    Energy Technology Data Exchange (ETDEWEB)

    Patricia Paviet-Hartmann; Catherine Riddle; Keri Campbell; Edward Mausolf

    2013-10-01

    Most of the aqueous processes developed, or under consideration worldwide for the recycling of used nuclear fuel (UNF) utilize the oxido-reduction properties of actinides to separate them from other radionuclides. Generally, after acid dissolution of the UNF, (essentially in nitric acid solution), actinides are separated from the raffinate by liquid-liquid extraction using specific solvents, associated along the process, with a particular reductant that will allow the separation to occur. For example, the industrial PUREX process utilizes hydroxylamine as a plutonium reductant. Hydroxylamine has numerous advantages: not only does it have the proper attributes to reduce Pu(IV) to Pu(III), but it is also a non-metallic chemical that is readily decomposed to innocuous products by heating. However, it has been observed that the presence of high nitric acid concentrations or impurities (such as metal ions) in hydroxylamine solutions increase the likelihood of the initiation of an autocatalytic reaction. Recently there has been some interest in the application of simple hydrophilic hydroxamic ligands such as acetohydroxamic acid (AHA) for the stripping of tetravalent actinides in the UREX process flowsheet. This approach is based on the high coordinating ability of hydroxamic acids with tetravalent actinides (Np and Pu) compared with hexavalent uranium. Thus, the use of AHA offers a route for controlling neptunium and plutonium in the UREX process by complexant based stripping of Np(IV) and Pu(IV) from the TBP solvent phase, while U(VI) ions are not affected by AHA and remain solvated in the TBP phase. In the European GANEX process, AHA is also used to form hydrophilic complexes with actinides and strip them from the organic phase into nitric acid. However, AHA does not decompose completely when treated with nitric acid and hampers nitric acid recycling. In lieu of using AHA in the UREX + process, formohydroxamic acid (FHA), although not commercially available, hold

  4. Utilization of bio-resources through nuclear technology

    International Nuclear Information System (INIS)

    Tamikazu Kume

    2002-01-01

    Nuclear technology such as gamma-ray, eb and ion beams is widely use for the utilization of bio-resources. Irradiation using gamma ray from 60 Co and electron beam is commercially used for the sterilization and modification of materials. Polysaccharides such as chitosan, sodium alginate, carrageenan, cellulose, pectin were easily degraded by irradiation and induced various kinds of biological activities, i.e. anti-bacterial activity, elicitor activity, plant growth promotion, suppression of environmental stress on plants. Some carbohydrate derivatives, carboxymethylcellulose (CMC), carboxymethyl-starch and carboxymethyl-chitin/chitosan, can be crosslinked under certain radiation condition and produced the biodegradable hydrogel for medical and agricultural uses. Ion beams have also been applied for mutation breeding for medical and agricultural use. Ion beams have also been applied for mutation breeding and the production of positron-emitting isotopes such as 11 C, 13 N, etc. It was succeeded to induce several kinds of flower-color and flower-form mutants in chrysanthemum and carnation by ion beams that have never produced by gamma-ray. The positron emitting tracer imaging system (PETIS) has been developed to obtain a dynamic image of plant transport in situ. (Author)

  5. A study on the status of nuclear development and utilization in North Korea

    International Nuclear Information System (INIS)

    Choi, Young Myung; Oh, Keun Bae; Lee, Kwang Seok; Ham, Cheol Hoon; Lee, Byeong Uk; Lee, Jae Seong; Choi, Yeong Rok; Ko, Han Seong

    1994-01-01

    The objective of this project is to propose strategies and tactics for nuclear cooperation between the South and the North in the perspective of the unification of the Korean Peninsula, based on proper and objective understanding of the status of nuclear development and utilization activities in North Korea, especially those for peaceful purposes. This study analyzes the nuclear development and utilization status of North Korea in terms of nuclear development history and policies, nuclear research and development, nuclear power generation, nuclear fuel cycle, production and uses of radiation and isotopes, manufacturing of equipment and components of nuclear power plants, and international nuclear cooperation. Based on the analysis, this study proposes basic directions for nuclear cooperation between South and North Korea. (Author)

  6. Differentiation between healthy thyroid remnants and tumor tissue after radioiodine therapy in patients with differentiated thyroid carcinoma using in-vitro phosphorus-31 magnetic resonance spectroscopy

    International Nuclear Information System (INIS)

    Moka, D.; Dietlein, M.; Schicha, H.; Raffelt, K.; Hahn, J.

    2002-01-01

    Full text: In many tumors, tumor growth and spread is triggered by changes in cell membrane metabolism, which can lead to systemic alterations in levels of phospholipids. The aim of this study was to differentiate between healthy remnants of thyroid tissue and residual/recurrent tumor tissue or metastases in patients with thyroid carcinoma by measurement of plasma levels of various phospholipids. Phospholipid concentrations was measured by in-vitro phosphorus-31-magnetic resonance spectroscopy ( 31 P-MRS) in blood samples from 30 patients with thyroid cancer, who had been rendered hypothyroid in preparation for diagnostic/therapeutic administration of iodine-131. All patients were already thyroidectomized. 131 I-whole-body scintigraphy and measurements of thyroglobulin values in a 2-year-follow-up were used to distinguish between patients in remission, patients with only healthy thyroid remnants and patients with cancerous thyroid tissue and/or metastases. Significantly lower blood plasma levels of systemic sphingomyelin (0.33±0.06 vs. 0.46±0.03 (controls) mmol/l; p 31 P-MRS can be used to differentiate between the presence of tumor tissue, healthy remnants of thyroid tissue not requiring further treatment and remission in patients with thyroid cancer. In future, therefore, plasma 31 P-MRS could be developed as an additional diagnostic tool for the follow-up of differentiated thyroid cancer. (author)

  7. Real-time graphic display utility for nuclear safety applications

    International Nuclear Information System (INIS)

    Yang, S.; Huang, X.; Taylor, J.; Stevens, J.; Gerardis, T.; Hsu, A.; McCreary, T.

    2006-01-01

    With the increasing interests in the nuclear energy, new nuclear power plants will be constructed and licensed, and older generation ones will be upgraded for assuring continuing operation. The tendency of adopting the latest proven technology and the fact of older parts becoming obsolete have made the upgrades imperative. One of the areas for upgrades is the older CRT display being replaced by the latest graphics displays running under modern real time operating system (RTOS) with safety graded modern computer. HFC has developed a graphic display utility (GDU) under the QNX RTOS. A standard off-the-shelf software with a long history of performance in industrial applications, QNX RTOS used for safety applications has been examined via a commercial dedication process that is consistent with the regulatory guidelines. Through a commercial survey, a design life cycle and an operating history evaluation, and necessary tests dictated by the dedication plan, it is reasonably confirmed that the QNX RTOS was essentially equivalent to what would be expected in the nuclear industry. The developed GDU operates and communicates with the existing equipment through a dedicated serial channel of a flat panel controller (FPC) module. The FPC module drives a flat panel display (FPD) monitor. A touch screen mounted on the FPD serves as the normal operator interface with the FPC/FPD monitor system. The GDU can be used not only for replacing older CRTs but also in new applications. The replacement of the older CRT does not disturb the function of the existing equipment. It not only provides modern proven technology upgrade but also improves human ergonomics. The FPC, which can be used as a standalone controller running with the GDU, is an integrated hardware and software module. It operates as a single board computer within a control system, and applies primarily to the graphics display, targeting, keyboard and mouse. During normal system operation, the GDU has two sources of data

  8. Utilities get more involved in Inpo [Institute of Nuclear Power Operations

    International Nuclear Information System (INIS)

    Varley, J.

    1984-01-01

    The Institute of Nuclear Power Operations (INPO) was established four years ago in a bid to foster self improvement and self regulation among the American nuclear power utilities. A significant increase in utility commitment and involvement in many of its programmes appears to have made 1983 a very good year for INPO. (U.K.)

  9. Utilization of analytical techniques in aid the implantation of nuclear installations

    International Nuclear Information System (INIS)

    Ferreira, M.P.; Sabino, C.V.S.; Avelar, M.M.

    1984-01-01

    Nuclear, physico-chemical and classic techniques developed and utilized by Centro de Desenvolvimento de Tecnicas Nucleares are presented, as back up to the implementation and operation of nuclear installations related with several parts of fuel cycle from uranium prospecting to waste treatment samples of soils, ores, alloys, plastics, paints, biological materials, air and water were analysed. (M.C.K) [pt

  10. 15 N utilization in nitride nuclear fuels for advanced nuclear power reactors and accelerator - driven systems

    International Nuclear Information System (INIS)

    Axente, D.

    2005-01-01

    15 N utilization for nitride nuclear fuels production for nuclear power reactors and accelerator - driven systems is presented. Nitride nuclear fuel is the obvious choice for advanced nuclear reactors and ADS because of its favorable properties: a high melting point, excellent thermal conductivity, high fissile density, lower fission gas release and good radiation tolerance. The application of nitride fuels in nuclear reactors and ADS requires use of 15 N enriched nitrogen to suppress 14 C production due to (n,p) reaction on 14 N. Accelerator - driven system is a recent development merging of accelerator and fission reactor technologies to generate electricity and transmute long - lived radioactive wastes as minor actinides: Np, Am, Cm. A high-energy proton beam hitting a heavy metal target produces neutrons by spallation. The neutrons cause fission in the fuel, but unlike in conventional reactors, the fuel is sub-critical and fission ceases when the accelerator is turned off. Nitride fuel is a promising candidate for transmutation in ADS of minor actinides, which are converted into nitrides with 15 N for that purpose. Tacking into account that the world wide market is about 20 to 40 Kg 15 N annually, the supply of that isotope for nitride fuel production for nuclear power reactors and ADS would therefore demand an increase in production capacity by a factor of 1000. For an industrial plant producing 100 t/y 15 N, using present technology of isotopic exchange in NITROX system, the first separation stage of the cascade would be fed with 10M HNO 3 solution of 600 mc/h flow - rate. If conversion of HNO 3 into NO, NO 2 , at the enriching end of the columns, would be done with gaseous SO 2 , for a production plant of 100 t/y 15 N a consumption of 4 million t SO 2 /y and a production of 70 % H 2 SO 4 waste solution of 4.5 million mc/y are estimated. The reconversion of H 2 SO 4 into SO 2 in order to recycle of SO 2 is a problem to be solved to compensate the cost of SO 2

  11. Nuclear waste disposal utilizing a gaseous core reactor

    Science.gov (United States)

    Paternoster, R. R.

    1975-01-01

    The feasibility of a gaseous core nuclear reactor designed to produce power to also reduce the national inventories of long-lived reactor waste products through nuclear transmutation was examined. Neutron-induced transmutation of radioactive wastes is shown to be an effective means of shortening the apparent half life.

  12. Problems associated with nuclear energy utilization in developing countries

    International Nuclear Information System (INIS)

    Aybers, N.

    1975-01-01

    The special problems of integrating nuclear power into the overall national power system of a developing country are reviewed. Topics such as optimal size selection, policy for nuclear fuel cycle, and choice of reactor type are examined. The results of these analyses as applied to Turkey are presented. The impact of safety and regulatory matters are discussed

  13. Demand for engineering manpower at US nuclear utilities, 1987-1997

    International Nuclear Information System (INIS)

    Poling, D.Y.

    1988-01-01

    The Institute of Nuclear Power Operations (INPO), organized in December 1979, is an independent undertaking in self-improvement by the US nuclear utilities. INPO has conducted manpower surveys each year since 1981. The survey is designed to determine current employment, vacancies, turnover, and other employment-related matters at the 54 US electric utilities that operate or are constructing nuclear power plants. It also provides 10-yr projections of nuclear manpower demand at the utilities and current and 1-yr projections of employment opportunities for new engineering and science graduates. It should be noted that the data reported in this paper do not include nonutility employment; utility employment constitutes approximately one-third of the civilian nuclear work force as reported by the US Department of Energy

  14. Owners of nuclear power plants: Percentage ownership of commercial nuclear power plants by utility companies

    International Nuclear Information System (INIS)

    Wood, R.S.

    1987-08-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of June 1, 1987. The list includes all plants licensed to operate, under construction, docked for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally canceled. In many cases, ownership may be in the process of changing as a result of altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants/licensees and percentage ownership. Part II lists applicants/licensees alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses (OL's). Footnotes for both parts appear at the end of this document

  15. Utilization of nuclear power in oceans and its perspective

    International Nuclear Information System (INIS)

    Yamaji, Akio

    2000-01-01

    Since 1959, Russia retains many nuclear icebreakers and has a plan to construct two new types of nuclear icebreakers. In Japan, research for advanced marine reactors and its fundamental studies are being conducted by the Japan Atomic Energy Research Institute (JAERI), the Ship Research Institute (SRI) and universities. The advanced marine reactor MRX designed by JAERI is a lightweight and compact integral PWR with a passive decay heat removal system. The Shipbuilding Research Association of Japan (JSRA) and the Japan Atomic Industrial Forum (JAIF) took a survey of the future nuclear ships and conducted an investigation of the total system related to the operation of nuclear ships, respectively, commissioned by JAERI. The committee of JSRA has recommended the displacement type of a large high-speed container ship promises to act as the next generation nuclear merchant ship. In the committee of JAIF, the cost evaluation has been made for a high-speed, large container ship equipped with two MRXs sailing the Pacific Ocean, and it is found that it could have an advantage economically over the diesel in some future conditions. The committee of JSRA has also recommended the deep-sea research vessel has been identified as a promising form for the next generation nuclear special-purpose ship, since the deep-sea represents a vast frontier in terms of basic scientific understanding of the earth. Many countries including Russia, Japan and U.S.A. are conducting a research of reactors for deep-sea vessels. The U.S. Navy made available nuclear powered submarines for civilian oceanographic research and the submarines were used in the Scientific Ice Expedition (SCICEX) program from 1995 to 1999. For floating nuclear power plant, the design of nuclear co-generation plant Pevek' for remote regions of Russia is completed using KLT-40C, based on a marine reactor. In Japan, fundamental studies of floating plants are being performed by private companies and JAERI. The designs of floating

  16. Utilization of nuclear power in oceans and its perspective

    Energy Technology Data Exchange (ETDEWEB)

    Yamaji, Akio [Ship Research Institute, Ministry of Transport, Mitaka, Tokyo (Japan)

    2000-03-01

    Since 1959, Russia retains many nuclear icebreakers and has a plan to construct two new types of nuclear icebreakers. In Japan, research for advanced marine reactors and its fundamental studies are being conducted by the Japan Atomic Energy Research Institute (JAERI), the Ship Research Institute (SRI) and universities. The advanced marine reactor MRX designed by JAERI is a lightweight and compact integral PWR with a passive decay heat removal system. The Shipbuilding Research Association of Japan (JSRA) and the Japan Atomic Industrial Forum (JAIF) took a survey of the future nuclear ships and conducted an investigation of the total system related to the operation of nuclear ships, respectively, commissioned by JAERI. The committee of JSRA has recommended the displacement type of a large high-speed container ship promises to act as the next generation nuclear merchant ship. In the committee of JAIF, the cost evaluation has been made for a high-speed, large container ship equipped with two MRXs sailing the Pacific Ocean, and it is found that it could have an advantage economically over the diesel in some future conditions. The committee of JSRA has also recommended the deep-sea research vessel has been identified as a promising form for the next generation nuclear special-purpose ship, since the deep-sea represents a vast frontier in terms of basic scientific understanding of the earth. Many countries including Russia, Japan and U.S.A. are conducting a research of reactors for deep-sea vessels. The U.S. Navy made available nuclear powered submarines for civilian oceanographic research and the submarines were used in the Scientific Ice Expedition (SCICEX) program from 1995 to 1999. For floating nuclear power plant, the design of nuclear co-generation plant Pevek' for remote regions of Russia is completed using KLT-40C, based on a marine reactor. In Japan, fundamental studies of floating plants are being performed by private companies and JAERI. The designs of

  17. Analysis and evaluation for social acceptability for utilizing nuclear power in China

    International Nuclear Information System (INIS)

    Xu, Ting; Wakabayashi, Toshio

    2011-01-01

    This study is about the acceptability of the society of utilizing nuclear power in China. There are different interactions and opinions has been raised that leads conflict between the society and the nuclear technology people. Many emotions and views have mixed up: people have image of environment friendly, also have image of explosion, fright and danger. The purpose of this study is to make clear the social consciousness for utilizing nuclear power in China and to improve social acceptability. A survey by the questionnaire was conducted for investigation of the features of the social consciousness for necessity and safety for utilizing nuclear power in China. The questionnaire has been sent to 10000 citizens of Zhejiang province in south China from June to August 2010 (Zhejiang province is one of the earliest city for utilizing nuclear power plants in China). There were 4255 available respondents (42.6%) with 1851 men and 2404 women of adult who answered the questionnaire. The survey was including 37 items about energy problem, social consciousness for utilizing nuclear power, safety, the reliability of government and information sources. As a result, it was found that some 57.5% of adults are in favor of nuclear power plants. There are differences of sense between men and women. The reliability for safety of men for nuclear power is higher than that of women. Some 59.6% of men respondents are in favor of nuclear power plants, and about 10% respondents of women are in favor of nuclear power plants. Social acceptance is still one of the major barriers for further development of nuclear power, although recent technological and institutional innovation is clearly reduced its risk and enhanced its relative and absolute benefit compared to other energy resources. Consequently, this result indicates that women with maternal instinct may not be favor of nuclear power plants compared with men in China. (author)

  18. Prospects for utilization of nuclear power in Africa

    Energy Technology Data Exchange (ETDEWEB)

    Polliart, A -J; Goodman, E [International Atomic Energy Agency, Division of Nuclear Power and Reactors, Vienna (Austria)

    1976-02-15

    Electric energy plays a key role in developing the infrastructure of countries all over the world, and increase in consumption of electricity is a definite indicator of economic development. Although there is no nuclear power plant in Africa yet, it is not too early for long-term planning of the role of nuclear energy in fulfilling the electricity demands of the future economies of African countries. A realistic assessment of the future role of nuclear power in a given electric system requires much more than the determination of an economically optimal plant mix. It calls for optimization under a series of constraints. Among these are licensing and regulatory factors, public attitudes and the degree of commitment to nuclear power by national governments. For many developing countries, the problems of financing additional foreign exchange expenditures are so acute as to force them to defer otherwise highly profitable ventures. In the case of nations with large low-cost fossil fuel and hydro resources a great degree of flexibility has been and is likely to be maintained in establishing medium and long-term objectives for nuclear energy. (author)

  19. The Maryland nuclear science baccalaureate degree program: The utility perspective

    International Nuclear Information System (INIS)

    Mueller, J.R.

    1989-01-01

    In the early 1980s, Wisconsin Public Service Corporation (WPSC) made a firm commitment to pursue development and subsequent delivery of an appropriate, academically accredited program leading to a baccalaureate degree in nuclear science for its nuclear operations personnel. Recognizing the formidable tasks to be accomplished, WPSC worked closely with the University of Maryland University College (UMUC) in curriculum definition, specific courseware development for delivery by computer-aided instruction, individual student evaluation, and overall program implementation. Instruction began on our nuclear plant site in the fall of 1984. The university anticipates conferring the first degrees from this program at WPSC in the fall of 1989. There are several notable results that WPSC achieved from this degree program. First and most importantly, an increase in the level of education of our employees. It should be stated that this program has been well received by WPSC operator personnel. These employees, now armed with plant experience, a formal degree in nuclear science, and professional education in management are real candidates for advancement in our nuclear organization

  20. Concept of automated system for spent fuel utilization ('Reburning') from compact nuclear reactors

    International Nuclear Information System (INIS)

    Ianovski, V.V.; Lozhkin, O.V.; Nesterov, M.M.; Tarasov, N.A.; Uvarov, V.I.

    1997-01-01

    On the basic concept of an automated system of nuclear power installation safety is developed the utilization project of spent fuel from compact nuclear reactors. The main features of this project are: 1. design and creation of the mobile model-industrial installation; 2. development of the utilization and storage diagram of the spent fuel from compact nuclear reactors, with the specific recommendation for the natatorial means using both for the nuclear fuel reburning, for its transportation in places of the storage; 3. research of an opportunity during the utilization process to obtain additional power resources, ozone and others to increase of justifying expenses at the utilization; 4. creation of new generation engineering for the automation of remote control processes in the high radiation background conditions. 7 refs., 1 fig

  1. Utilities press Congress to salvage nuclear R and D

    International Nuclear Information System (INIS)

    Crawford, M.

    1986-01-01

    A proposal to reduce DOE's advanced civilian reactor research and expand military work worries nuclear industry. The Reagan Administration has emphasized high-risk, long term research over applied research and demonstrations on the grounds that industry should be responsible for technology development. The proposed fiscal year 1987 budget for civilian reactor research is $222.5 million, a deep cut below this year's budget of $319.7 million. Funding for advanced reactor research and development alone shows a 61.5% reduction to $49.5 million. With this grim budget outlook, funding restorations may have to be gotten from other nuclear research programs

  2. Proposing and Planning the Rehabilitation Works of Mechanical Utility System in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Jusnan Hasim; Mohamad Suhaimi Yahaya; Abdul Razak Hashim

    2015-01-01

    Nuclear Malaysia has 2 complex located in Bangi and Jalan Dengkil. The utility in Nuclear Malaysia consists of civil, mechanical and electrical system that has been managed by Bahagian Kejuruteraan (BKJ). The mechanical utilities system has been divided to three main groups which are the main system, supporting system and safety equipment's. The objectives of this paper are to propose and plan the rehabilitation works of mechanical utility system in Nuclear Malaysia and also to explain working procedures in maintaining and repairing the mechanical utility system. The study suggest the rehabilitation works on the mechanical utilities system especially on Thermal Energy Storage (TES) and domestic water system needs to be done which involve process of design, procurement, installation and commissioning. (author)

  3. Investigation into the risk perceptions of investors in the securities of nuclear-dependent electric utilities

    International Nuclear Information System (INIS)

    Spudeck, R.E.

    1983-01-01

    Two weeks prior to the Three Mile Island accident, March 15, 1979, the Nuclear Regulatory Commission ordered five operating nuclear plants shut down in order to reexamine safety standards in these plants. Reports in the popular and trade press during this time suggested that these events, particularly the accident at Three Mile Island, caused investors in the securities of electric utilities that had nuclear-generation facilities to revise their risk perceptions. This study was designed to examine the impact of both the Nuclear Regulatory Commission order and the accident at Three Mile Island on investor risk perceptions. Selected categories of electric utilities were chosen to examine any differential risk effects resulting from these events. An asset pricing model devoid of many of the restrictive assumptions of more familiar models was used to model investor behavior. The findings suggest that the events described did cause investors to revise upward their perceptions of systematic risk regarding different categories of electric utilities. More specifically, those electric utilities that were operating nuclear plants in 1979 experienced the largest and most sustained increase in systematic risk. However, electric utilities that in 1979 had no operating nuclear plants, but had planned and committed funds for nuclear plants in the future, also experienced increases in systematic risk

  4. The study for effective utilization on the nuclear information of OECD/NEA

    International Nuclear Information System (INIS)

    Ko, H. S.; Oh, K. B.; Lee, H. M.

    2001-01-01

    As a group of nuclear-advanced countries, the OECD/NEA mainly deals with the aspects of science and technology and future policy of nuclear energy. It is very important for us to develop nuclear advanced technology and enhance the global environemnt of nuclear utilization and development through the OECD/NEA. It is required for us to timely obtain and analyse the up-to-date nuclear technology information and to build up a system to collect and distribute nuclear technology information from NEA committees. In this study, measures for effective utilization of the NEA information have been established through the analysis of the activities of the experts meeting in each standing technical committee and of technology information. In this regard, it is also developed a homepage to disseminate reports from NEA Committees participants as one of the strengthening measures

  5. Some possibilities for improvement of fuel utilization in nuclear power plants

    International Nuclear Information System (INIS)

    Kocic, A.; Marinkovic, N.

    1983-01-01

    Methods for improving the nuclear fuel utilization with the emphasis on LWRs are being dealt with in this paper. Some basic results concerning tubular fuel pellets of the Krsko nuclear power plants are presented, showing promising possibilities for uranium saving from the neutronics point of view. (author)

  6. Proposed advanced satellite applications utilizing space nuclear power systems

    International Nuclear Information System (INIS)

    Bailey, P.G.; Isenberg, L.

    1990-01-01

    A review of the status of space nuclear reactor systems and their possible applications is presented. Such systems have been developed over the past twenty years and are capable of use in various military and civilian applications in the 5-1000 kWe power range. The capabilities and limitations of the currently proposed nuclear reactor systems are summarized. Safety issues are shown to be identified, and if properly addressed should not pose a hindrance. Applications are summarized for the federal and civilian community. These applications include both low and high altitude satellite surveillance missions, communications satellites, planetary probes, low and high power lunar and planetary base power systems, broad-band global telecommunications, air traffic control, and high-definition television

  7. Impact of accidents on organizational aspects of nuclear utilities

    OpenAIRE

    Spurgin, A. J.; Stupples, D.

    2012-01-01

    This paper applies the Beer Viable Systems Model (VSM) approach to the study of nuclear accidents. It relates how organizational structures and rules are affected by accidents in the attempt to improve safety and reduce risk. The paper illustrates this process with reference to a number of accidents. The dynamic cybernetic aspect of the VSM approach to organizations yields a better understanding of the need for good decision-making to minimize risk and how organizations really operate.

  8. Utilization of nuclear research reactors in forensic science - Indian scenario

    International Nuclear Information System (INIS)

    Basu, A.K.; Tripathi, A.B.R.; Bhadkambekar, C.A.; Arya, Bharti; Chattopadhyay, N.

    2009-01-01

    Nuclear analytical techniques in Forensic Science is one of the most important fields of peaceful applications of atomic energy for societal cause. Forensic Science is oriented towards the examination of evidence specimens, collected from a scene of crime in order to establish the link between the suspect/criminal and the crime. This science therefore has a profound role to play in criminal justice delivery system. (author)

  9. Utilization of nuclear power - a sustainable error of history?

    International Nuclear Information System (INIS)

    Gugerli, D.

    2004-01-01

    The history of atomic energy has been producing major surprises for at least half a century. A wave of atomic enthusiasm - which grew to a veritable atomic euphoria - was triggered by the famous atoms-for-peace speech by US president Eisenhower in 1953. Despite their inherent technocratic pacifism, Eisenhower's atoms led to critical conflicts within those societies that subscribed to the nuclear development scheme. A critical revision of these conflicts reveals a dramatic falling apart of the historic horizon of expectations and the historic development path. Notwithstanding, both the apologists of nuclear energy use and their antagonists have erred in many ways without truly losing their capacity to act. They misjudged the planning security, the safety of the installations, and the stability of the price relations on the energy and capital equipment markets. Moreover, both sides erred in their predictions concerning the political conditions and the social consequences of nuclear power plants. This observation is not historically insightful in the sense of learning from one's mistakes. It is insightful rather for the relationship between experience, expectation and decision on the one hand and socio-technical change on the other hand. (orig.)

  10. Membrane steam reforming of natural gas for hydrogen production by utilization of medium temperature nuclear reactor

    International Nuclear Information System (INIS)

    Djati Hoesen Salimy

    2010-01-01

    The assessment of steam reforming process with membrane reactor for hydrogen production by utilizing of medium temperature nuclear reactor has been carried out. Difference with the conventional process of natural gas steam reforming that operates at high temperature (800-1000°C), the process with membrane reactor operates at lower temperature (~500°C). This condition is possible because the use of perm-selective membrane that separate product simultaneously in reactor, drive the optimum conversion at the lower temperature. Besides that, membrane reactor also acts the role of separation unit, so the plant will be more compact. From the point of nuclear heat utilization, the low temperature of process opens the chance of medium temperature nuclear reactor utilization as heat source. Couple the medium temperature nuclear reactor with the process give the advantage from the point of saving fossil fuel that give direct implication of decreasing green house gas emission. (author)

  11. Incentive regulation of nuclear power plants by state Public Utility Commissions

    International Nuclear Information System (INIS)

    Martin, R.L.; Olson, J.; Hendrickson, P.

    1989-12-01

    Economic performance incentives established by state Public Utility Commissions (PUCs) currently are applicable to the construction or operation of approximately 73 nuclear power reactors owned by 27 utilities with investment greater than 10% in 18 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its headquarters and regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report on incentive regulation of nuclear power plants by state PUCs presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant

  12. Incentive regulation of nuclear power plants by state public utility commissions

    International Nuclear Information System (INIS)

    Petersen, J.C.

    1987-12-01

    This report on incentive regulation of nuclear power plants by state public utility commissions (PUCs). Economic performance incentives established by state PUCs are applicable to the construction or operation of about 45 nuclear power reactors owned by 30 utilities in 17 states. The NRC staff monitors development of the incentives and periodically provides an updated report on all nuclear plant incentives to its regional offices. The staff maintains contact with the PUCs and the utilities responsible for implementing the incentives in order to obtain the updated information and to consider potential safety effects of the incentives. This report presents the NRC staff's concerns on potential safety effects of economic performance incentives. It also includes a plant-by-plant survey that describes the mechanics of each incentive and discusses the financial effects of the incentive on the utility-owner(s) of the plant

  13. Cellular applications of 31P and 13C nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Shulman, R.G.; Brown, T.R.; Ugurbil, K.; Ogawa, S.; Cohen, S.M.; den Hollander, J.A.

    1979-01-01

    High-resolution nuclear magnetic resonance (NMR) studies of cells and purified mitochondria are discussed to show the kind of information that can be obtained in vivo. In suspensions of Escherichia coli both phosphorus-31 and carbon-13 NMR studies of glycolysis of bioenergetics are presented. In rat liver cells the pathways of gluconeogenesis from carbon-13-labeled glycerol are followed by carbon-13 NMR. In the intact liver cells cytosolic and mitochondrial pH's were separately measured by phosphorus-31 NMR. In purified mitochondria the internal and external concentrations of inorganic phosphate, adenosine diphosphate, and adenosine triphosphate were determined by phosphorus-31 while the pH difference across the membrane was measured simultaneously

  14. Global evaluation of nuclear infrastructure utilization scenarios (GENIUS)

    International Nuclear Information System (INIS)

    unzik-Gougar, Mary Lou; Juchau, Christopher A.; Pasamehmetoglu, Kemal; Wilson, Paul P.H.; Oliver, Kyle M.; Turinsky, Paul J.; Abdel-Khalik, Hany S.; Hays, Ross; Stover, Tracy E.

    2007-01-01

    A new and unique fuel cycle systems code has been developed. Need for this analysis tool was established via methodical development of technical functions and requirements followed by an evaluation of existing fuel cycle codes. As demonstrated by analysis of GNEP-type scenarios, the GENIUS code discretely tracks nuclear material from beginning to end of the fuel cycle and among any number of independent regions. Users can define scenarios starting with any/all existing reactors and fuel cycle facilities or with an ideal futuristic arrangement. Development and preliminary application of GENIUS capabilities in uncertainty analysis/propagation and multi-parameter optimization have also been accomplished. (authors)

  15. Physics of future equilibrium state of nuclear energy utilization

    International Nuclear Information System (INIS)

    Sekimoto, H.

    1994-01-01

    The governing equations for future equilibrium nuclear state are presented and their characteristics are discussed. These equations are solved for several typical cases. In the present study on the equilibrium state, two coincidences are found. The first is the coincidence on the neutron balance performed by the nuclides satisfying the equilibrium condition. The finite neutron multiplication factor is near unity. The second is the coincidence on the toxicity. The produced long-life fission product toxicity is near the incinerated natural fuel toxicity. (author). 2 refs., 2 tabs., 4 figs

  16. Future nuclear energy utilization in view of the Swiss economy

    International Nuclear Information System (INIS)

    Kuendig, M.

    1990-01-01

    The tried and proven system of dividing duties between government and business should be continued. A double 'no', preserving the legal basis for the future use of nuclear energy, should therefore be the answer to the two bills aimed against it in Switzerland. Conservation, research and substitution efforts of private industry can be rewarded by providing the necessary framework. The creation of indirect incentives should further support these efforts, without federal intervention. For this reason and with the same resoluteness, the 'energy article' has to be rejected. (author)

  17. Human resource development for nuclear generation - from the perspective of a utility company

    Science.gov (United States)

    Kahar, Wan Shakirah Wan Abdul; Mostafa, Nor Azlan; Salim, Mohd Faiz

    2017-01-01

    Malaysia is currently in the planning phase of its nuclear power program, with the first unit targeted to be operational in 2030. Training of nuclear power plant (NPP) staffs are usually long and rigorous due to the complexity and safety aspects of nuclear power. As the sole electricity utility in the country, it is therefore essential that Tenaga Nasional Berhad (TNB) prepares early in developing its human resource and nuclear expertise as a potential NPP owner-operator. A utility also has to be prudent in managing its work force efficiently and effectively, while ensuring that adequate preparations are being made to acquire the necessary nuclear knowledge with sufficient training lead time. There are several approaches to training that can be taken by a utility company with no experience in nuclear power. These include conducting feasibility studies and benchmarking exercises, preparing long term human resource development, increasing the exposure on nuclear power technology to both the top management and general staff, and employing the assistance of relevant agencies locally and abroad. This paper discusses the activities done and steps taken by TNB in its human resource development for Malaysia's nuclear power program.

  18. Proceedings of international workshop on utilization of nuclear power in oceans (N'ocean 2000)

    International Nuclear Information System (INIS)

    Yamaji, A.; Nariyama, N.; Sawada, K.

    2000-03-01

    Human beings and the ocean have maintained close relations for a long time. The ocean produced the life at very old time and human beings have been benefited by ocean, particularly in Japan that is surrounded by the ocean. In the utilization of nuclear power in ocean, Japan has been very active from the beginning of the development of nuclear power. The nuclear powered ship MUTSU has been developed and completed the experimental voyage. Besides the nuclear powered ship, we are using the ocean for the transportation of radioactive materials. This International Workshop aimed at offering further information about nuclear utilization in oceans such as icebreakers, deep-sea submarines, high speed carriers, floating plant, desalination and heating plants, radioactive materials transport ships, and so on. The discussions on the economical, environmental and scientific effects are included. The 36 of the present papers are indexed individually. (J.P.N.)

  19. National strategic planing for the utilization and development of nuclear energy

    International Nuclear Information System (INIS)

    Won, B. C.; Lee, Y. J.; Lee, T. H.; Oh, K. B.; Kim, S. H.; Lee, J. W.

    2011-12-01

    It is followed that results and contents of National strategic planning for the utilization and development of nuclear energy. Our team makes an effort to carry out pre-research on establishment of the fourth Comprehensive Nuclear Energy Promotion Plan(CNEPP). To establish CNEPP, we analyzed domestic and global environment and trends of nuclear energy including the result of patent analysis, and find ways to link and coordinate other national plans concerned with nuclear energy. Upon the analysis we produce the final draft absorbing comments from the above-mentioned public discussions

  20. Method for utilizing decay heat from radioactive nuclear wastes

    International Nuclear Information System (INIS)

    Busey, H.M.

    1974-01-01

    Management of radioactive heat-producing waste material while safely utilizing the heat thereof is accomplished by encapsulating the wastes after a cooling period, transporting the capsules to a facility including a plurality of vertically disposed storage tubes, lowering the capsules as they arrive at the facility into the storage tubes, cooling the storage tubes by circulating a gas thereover, employing the so heated gas to obtain an economically beneficial result, and continually adding waste capsules to the facility as they arrive thereat over a substantial period of time

  1. The application of utility analysis processes to estimate the impact of training for nuclear maintenance personnel

    International Nuclear Information System (INIS)

    Groppel, C.F.

    1991-01-01

    The primary objectives of this study were to test two utility analysis models, the Cascio-Ramos Estimate of Performance in Dollars (CREPID) model and Godkewitsch financial utility analysis model and to determine their appropriateness as tools for evaluating training. This study was conducted in conjunction with Philadelphia Electric Company's Nuclear Training Group. Job performance of nuclear maintenance workers was assessed to document the impact of the training program. Assessment of job performance covered six job performance themes. Additionally, front-line nuclear maintenance supervisors were interviewed to determine their perceptions of the nuclear maintenance training. A comparison of supervisor's perceptions and outcomes of the utility analysis models was made to determine the appropriateness of utility analysis as quantitative tools for evaluating the nuclear maintenance training program. Application of the CREPID utility analysis model indicated the dollar value of the benefits of training through utility analysis was $5,843,750 which represented only four of the job performance themes. Application of the Godkewitsch utility analysis model indicated the dollar value of the benefits of training was $3,083,845 which represented all six performance themes. A comparison of the outcomes indicated a sizeable difference between the dollar values produced by the models. Supervisors indicated training resulted in improved productivity, i.e., improved efficiency and effectiveness. Additionally, supervisors believed training was valuable because it provided nonmonetary benefits, e.g., improved self-esteem and confidence. The application of utility analysis addressed only monetary benefits of training. The variation evidenced by the difference in the outcome of the two models suggests that utility analysis open-quotes estimatesclose quotes may not accurately reflect the impact of training

  2. Hydrogen research and nuclear safety: a utility perspective

    International Nuclear Information System (INIS)

    Lau, W.

    1982-01-01

    The main thrust of this paper is to emphasize that research efforts need to be pursued only after the following steps have been taken: 1) identify clearly what decisions are needed; 2) develop an overall decision logic chart and identify the information required for each of the decisions; 3) distinguish confirmatory research from research needed for decision-making information; 4) recognize that an optimized mitigation system is generally not the objective, neither is minimum risk required; 5) assure that the level of studies be consistent with the risk. After having taken the above steps, the authors concluded that a deliberate and distributed ignition system is a viable solution for the hydrogen problem for certain nuclear power plants

  3. A ''New Generation'' of Nuclear Power Plants- Electric Utility Aspects

    International Nuclear Information System (INIS)

    Marouani, D.; Reznik, L.; Tavron, B.

    1999-01-01

    A 50% increase in worldwide energy consumption in the next 20 years is anticipated, due to the global population growth and to higher standards of living. Meeting these energy demands with the fossil energy sources such as coal. gas and oil may lead to atmospheric accumulation of greenhouse gases, resulting in global warming of several degrees with catastrophic climatic consequences. Implementation of various energy conservation measures may bring only insignificant reduction in demand levels. Hopes that the renewable energy sources (such as hydroelectric, solar, wind power, biomass and geothermal) may supply the growth in the demand - are unrealistic. Only nuclear power (providing already 16% of world electricity) may meet all the energy demand growth with negligible greenhouse emission

  4. The effect of the Fukushima nuclear accident on stock prices of electric power utilities in Japan

    International Nuclear Information System (INIS)

    Kawashima, Shingo; Takeda, Fumiko

    2012-01-01

    The purpose of this study is to investigate the effect of the accident at the Fukushima Daiichi nuclear power station, which is owned by Tokyo Electric Power Co. (TEPCO), on the stock prices of the other electric power utilities in Japan. Because the other utilities were not directly damaged by the Fukushima nuclear accident, their stock price responses should reflect the change in investor perceptions on risk and return associated with nuclear power generation. Our first finding is that the stock prices of utilities that own nuclear power plants declined more sharply after the accident than did the stock prices of other electric power utilities. In contrast, investors did not seem to care about the risk that may arise from the use of the same type of nuclear power reactors as those at the Fukushima Daiichi station. We also observe an increase of both systematic and total risks in the post-Fukushima period, indicating that negative market reactions are not merely caused by one-time losses but by structural changes in society and regulation that could increase the costs of operating a nuclear power plant.

  5. Present status of nuclear energy development and utilization in Japan 1994

    International Nuclear Information System (INIS)

    1994-03-01

    Today, world energy demands continue to increase, and over the middle and long-term, access to petroleum supplies may become difficult. At the same time, such serious environmental problems as global warming and acid rain, which are caused by the burning of fossil fuels, have drawn great public attention, and the international community has urged that solutions to them should be found. Because nuclear power offers an economically efficient, stable supply of energy whose production has little adverse effect on the environment, the world has recognized the necessity of continuing to develop and use it. The changing international political situation, however, has complicated nuclear energy matters. In Japan, particularly the collapse of the former Soviet Union and North Korea's announcement of its intention to withdraw from the Nuclear Weapons Non-Proliferation Treaty have been cause for concern. Under these circumstances, it has become increasingly important for Japan to secure stable sources of energy, since Japan is dependent on imports for its energy supply. To that end, Japan has steadily promoted the development and utilization of nuclear energy. In fiscal 1992, nuclear power accounted for 28.2 % of the total power generated by Japanese electric utilities. Japan has also worked steadily to develop a nuclear fuel cycle, which is important to the long-term stability of the energy supply. This publication describes the present status of nuclear energy development and utilization in Japan. (J.P.N.)

  6. Observed TRU data from nuclear utility waste streams

    International Nuclear Information System (INIS)

    Wessman, R.A.; Floyd, J.G.; Leventhal, L.

    1990-01-01

    TMA/Norcal has performed 10CFR61 analysis of radioactive waste streams from BWR's and PWR's since 1983. Many standard and non-routine sample types have been received for analysis from nuclear power plants nation-wide. In addition to the 10CFR61 Tables I and II analyses, we also have analyzed for many of the supplementary isotopes. As part of this program TRU analyses are required. As a result, have accumulated a significant amount of data for plutonium, americium, and curium in radioactive waste for many different sample matrices from many different waste streams. This paper will present our analytical program for 10CFR61 TRU. The laboratory methodology including chemical and radiometric procedures is discussed. The sensitivity of our measurements and ability to meet the lower limits of detection is also discussed. Secondly, a review of TRU data is presented. Scaling factors and their ranges from selected PWR stations are included. We discuss some features of, and limits to, interpretation of these data. 8 refs., 3 tabs

  7. Overview of reductants utilized in nuclear fuel reprocessing/recycling

    Energy Technology Data Exchange (ETDEWEB)

    Paviet-Hartmann, P. [Idaho National Laboratory, 995 University Blvd, Idaho Falls, ID 83402 (United States); Riddle, C. [Idaho National Laboratory, Material and Fuel Complex, Idaho Falls, ID 83415-6150 (United States); Campbell, K. [University of Nevada Las Vegas, 4505 S. Maryland Pkwy, Las Vegas, NV 89144 (United States); Mausolf, E. [Pacific Northwest National Laboratory, 902 Batelle Blvd, Richland, WA 99352 (United States)

    2013-07-01

    The most widely used reductant to partition plutonium from uranium in the Purex process was ferrous sulfamate, other alternates were proposed such as hydrazine-stabilized ferrous nitrate or uranous nitrate, platinum catalyzed hydrogen, and hydrazine, hydroxylamine salts. New candidates to replace hydrazine or hydroxylamine nitrate (HAN) are pursued worldwide. They may improve the performance of the industrial Purex process towards different operations such as de-extraction of plutonium and reduction of the amount of hydrazine which will limit the formation of hydrazoic acid. When looking at future recycling technologies using hydroxamic ligands, neither acetohydroxamic acid (AHA) nor formohydroxamic acid (FHA) seem promising because they hydrolyze to give hydroxylamine and the parent carboxylic acid. Hydroxyethylhydrazine, HOC{sub 2}H{sub 4}N{sub 2}H{sub 3} (HEH) is a promising non-salt-forming reductant of Np and Pu ions because it is selective to neptunium and plutonium ions at room temperature and at relatively low acidity, it could serve as a replacement of HAN or AHA for the development of a novel used nuclear fuel recycling process.

  8. Efforts to utilize risk assessment at nuclear power plants

    International Nuclear Information System (INIS)

    Narumiya, Yoshiyuki

    2015-01-01

    Risk assessment means the use of the outputs that have been obtained through risk identification and risk analysis (risk information), followed by the determination of the response policy by comparing these outputs with the risk of judgement standards. This paper discusses the use of risk information with multifaceted nature and its significance, and the challenges to the further penetration of these items. As the lessons and risk assessment learnt from the past accidents, this paper takes up the cases of the severe accidents of Three Mile Island, Chernobyl, and Fukushima Daiichi power stations, and discusses their causes and expansion factors. In particular, at Fukushima Daiichi Nuclear Power Station, important lessons were shortage in measures against the superimposition of earthquake and tsunami, and the insufficient use of risk assessment. This paper classified risk assessment from the viewpoint of risk information, and showed the contents and index for each item of risk reduction trends, risk increase trends, and measures according to the importance of risk. As the benefits of activities due to risk assessment, this paper referred to the application cases of the probabilistic risk assessment (PRA) of IAEA, and summarized the application activities of 10 items of risk indexes by classifying them to safety benefits and operational benefits. For example, in the item of flexible Allowed Outage Time (AOT), the avoidance of plant shutdown and the flexibility improvement of maintenance scheduling at a plant are corresponding to the above-mentioned benefits, respectively. (A.O.)

  9. Nuclear data adjustment methodology utilizing resonance parameter sensitivities and uncertainties

    International Nuclear Information System (INIS)

    Broadhead, B.L.

    1983-01-01

    This work presents the development and demonstration of a Nuclear Data Adjustment Method that allows inclusion of both energy and spatial self-shielding into the adjustment procedure. The resulting adjustments are for the basic parameters (i.e. resonance parameters) in the resonance regions and for the group cross sections elsewhere. The majority of this development effort concerns the production of resonance parameter sensitivity information which allows the linkage between the responses of interest and the basic parameters. The resonance parameter sensitivity methodology developed herein usually provides accurate results when compared to direct recalculations using existng and well-known cross section processing codes. However, it has been shown in several cases that self-shielded cross sections can be very non-linear functions of the basic parameters. For this reason caution must be used in any study which assumes that a linear relatonship exists between a given self-shielded group cross section and its corresponding basic data parameters. The study also has pointed out the need for more approximate techniques which will allow the required sensitivity information to be obtained in a more cost effective manner

  10. Safety Performance Improvement for Nuclear Power Plants Utilizing THOMAS

    International Nuclear Information System (INIS)

    Kim, Won June; Ryu, Jung Uk; Suh, Kune Y.

    2005-01-01

    THOMAS (Thermal Hydraulics Online Monitoring Advisory System) is equipped with a couple of salient features compared with existing monitoring systems. The first has to do with the three-dimensional (3D) visualization technique to support the nuclear power plant (NPP) operators and personnel using the virtual reality (VR) technology. VR depicts an environment simulated by a computer. Most of the VR environments primarily include visual experiences, displayed either on a monitor or though special stereoscopic goggles. Users can often interactively manipulate a VR environment, either through standard input devices like a keyboard, or through specially designed devices like a cybergloves. Additional devices were not applied the in THOMAS. The visualized model file is brought to the VR space from the computer-aided design (CAD) tool. In the VR space, using mapping, the component color is changed with linked value of the safety variables. Operators thus can easily recognize the plant condition. This is related with the human factor engineering. The second is the function of decision making using the influence diagram logic. The influence diagram logic is based on the total probability and Bayesian theory. The accident modeling is rooted in the emergency operating procedure (EOP). The final goal of this system is, in the accident situation, to present a success path to the operator for the recovery of the NPP system. At the current developing level, the database signals THOMAS. In other words, a spectrum of system analysis codes provides the safety parameter values to the database, which are subsequently supplied to THOMAS through the network

  11. Drug and alcohol abuse: the bases for employee assistance programs in the nuclear-utility industry

    Energy Technology Data Exchange (ETDEWEB)

    Radford, L.R.; Rankin, W.L.; Barnes, V.; McGuire, M.V.; Hope, A.M.

    1983-07-01

    This report describes the nature, prevalence, and trends of drug and alcohol abuse among members of the US adult population and among personnel in non-nuclear industries. Analogous data specific to the nuclear utility industry are not available, so these data were gathered in order to provide a basis for regulatory planning. The nature, prevalence, and trend inforamtion was gathered using a computerized literature, telephone discussions with experts, and interviews with employee assistance program representatives from the Seattle area. This report also evaluates the possible impacts that drugs and alcohol might have on nuclear-related job performance, based on currently available nuclear utility job descriptions and on the scientific literature regarding the impairing effects of drugs and alcohol on human performance. Employee assistance programs, which can be used to minimize or eliminate job performance decrements resulting from drug or alcohol abuse, are also discussed.

  12. Labor supply of engineers and scientists for nuclear electric utilities, 1987-1992

    International Nuclear Information System (INIS)

    Blair, L.M.

    1988-01-01

    An assessment of the adequacy of the supply of health physicists, nuclear engineers, and other engineers for the nuclear electric utility industry is based on job openings for scientists and engineers in broader nuclear-power-related fields, which include engineering and design, manufacturing, fabrication, supporting services, and government. In assessing the likely adequacy of labor supplies for commercial nuclear power job openings over the next 5 yr, consideration has been given to competing sources of labor demands, including nuclear energy research and development activities, nuclear defense, and the total US economy, and to the likely supply of new graduates. In particular, over the last 3 yr, the number of degrees awarded and enrollments in nuclear engineering programs have declined 12 and 14%, respectively, and in health physics programs, 5 and 14%, respectively. For health physics and nuclear engineers, tight labor market conditions (i.e. labor supplies and demand balanced at relatively high salaries) are expected over the next 5 yr because of declining enrollments and slowly growing employment levels plus job replacement needs. The commercial nuclear power field is expected to face tight labor markets for electrical and materials engineers because of strong competing demands in the economy. Other engineering occupations are likely to have adequate supplies for the nuclear power field but at salaries that continue to be relatively higher than salaries for other professional occupations

  13. Utilizing reliability concepts in the development of IEEE recommended good practices for nuclear plant maintenance

    International Nuclear Information System (INIS)

    Gradin, L.P.

    1986-01-01

    This paper presents information describing the concern for nuclear power plant electrical equipment maintenance and the IEEE Nuclear Power Engineering Committee's method to address that concern. That method includes the creation of Working Group 3.3, ''Maintenance Good Practices'' which is developing specific maintenance good practice documents, supporting technical information exchange, and providing a vehicle to promote practices which can reduce cost and enhance plant safety. The foundation for that effort is the utilization of Reliability concepts

  14. Exploratory study of nuclear reaction data utility framework of Japan charged particle reaction data group (JCPRG)

    International Nuclear Information System (INIS)

    Masui, Hiroshi; Ohnishi, Akira; Kato, Kiyoshi; Ohbayasi, Yosihide; Aoyama, Shigeyoshi; Chiba, Masaki

    2002-01-01

    Compilation, evaluation and dissemination are essential pieces of work for the nuclear data activities. We, Japan charged particle data group, have researched the utility framework for the nuclear reaction data on the basis of recent progress of computer and network technologies. These technologies will be not only for the data dissemination but for the compilation and evaluation assistance among the many corresponding researchers of all over the world. In this paper, current progress of our research and development is shown. (author)

  15. Development of a utility system for charged particle nuclear reaction data by using intelligentPad

    International Nuclear Information System (INIS)

    Aoyama, Shigeyoshi; Ohbayashi, Yoshihide; Masui, Hiroshi; Kato, Kiyoshi; Chiba, Masaki

    2000-01-01

    We have developed a utility system, WinNRDF2, for a nuclear charged particle reaction data of NRDF (Nuclear Reaction Data File) on the IntelligentPad architecture. By using the system, we can search the experimental data of a charged particle reaction of NRDF. Furthermore, we also see the experimental data by using graphic pads which was made through the CONTIP project. (author)

  16. Dosimetry of beta sources utilized in nuclear medicine and biomedicine

    International Nuclear Information System (INIS)

    Bergoc, R.M.; Rivera, E.; Cricco, G.; Martin, G.; Cocca, C.; Caro, R.A.

    1998-01-01

    Full text: The use of high energy pure beta sources (i.e., 32 P= 1.71 MeV/des) is common in medicine (intratumoral therapy or treatment of non-malignant illness as restenosis) and in biochemistry (molecular biology). The external dosimetry of these sources offers some important points that must be considered: 1) beta particles emitted by the source are not monoenergetic; 2) the range (R 0 ) vary with the source energy and the Z of the absorber; 3) below an energy of 1 MeV, the specific ionization in the absorbent medium (air, water, lucite) increases as the beta energy (E β ) decreases; 4) the range of beta particles, R β , is independent from Z of the material, provided Z is low and the material has no hydrogen; in this case, the expression: R β δ 1 = R β δ 2 is valid; 5) the calculation of the external beta dosimetry must consider that since the used sources are not punctual there is self-absorption which should be taken into account. However, in the range of the fractions of activities for the above mentioned practices a theoretical model for punctual sources can be used; in this case, it is valid to use the expression: Dose Rate: = A (S/δ)E β e -S/δ δx /4 π d 2 , where: (S/δ) is the absorbent Mass Stopping Power and represents the loss of energy by unit mass thickness; it depends from E β and it is independent from Z; (δx) is the mass thickness of the absorber. By this way, e -S/δ δx is the attenuation of the beta particles flow. From the application of this formula it can be deduced that, for sources of 1 mCi of 32 P activities, as those employed in biochemistry, a small thickness of lucite is enough shield. When the source has higher activities, as those used in radiotherapy, the operator should take into account the regulations for a strict dosimetric control. These formulae allow a simplified calculation of the 32 P dosimetry of sources used in nuclear medicine and biomedical practices. (author) [es

  17. Economics and utilization of thorium in nuclear reactors. Technical annexes 1 and 2

    International Nuclear Information System (INIS)

    1978-05-01

    An assessment of the impact of utilizing the 233 U/thorium fuel cycle in the U.S. nuclear economy is strongly dependent upon several decisions involving nuclear energy policy. These decisions include: (1) to recycle or not recycle fissile material; (2) if fissile material is recycled, to recycle plutonium, 233 U, or both; and (3) to deploy or not to deploy advanced reactor designs such as Fast Breeder Reactors (FBR's), High Temperature Gas Reactors (HTGR's), and Canadian Deuterium Uranium Reactors (CANDU's). This report examines the role of thorium in the context of the above policy decisions while focusing special attention on economics and resource utilization

  18. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1982

    International Nuclear Information System (INIS)

    1983-01-01

    The utilization of the facilities in the Japan Atomic Energy Research Institute in common in 1982 has finished in active state, and the results of the researches have reached the stage of publication. The subjects of the researches spread over wide fields, and in 1982 also, extremely diversified researches were carried out. In this report, theses results were collected in one book, and it is desirable to utilize it actively. The number of the research themes is 131. In the field of general researches, the researches on radiochemistry, the utilization of radiation and the effects of irradiation were mostly carried out, while in cooperative researches, the researches were mainly concerned with nuclear reactor engineering and nuclear reactor materials. The total number of visitors was 3025. The facilities offered to the common utilization were JRR-2, JRR-3, JRR-4, Co-60 irradiation facility and others. The abstracts of the papers are reported. (J.P.N.)

  19. Consensus standards utilized and implemented for nuclear criticality safety in Japan

    International Nuclear Information System (INIS)

    Nomura, Yasushi; Okuno, Hiroshi; Naito, Yoshitaka

    1996-01-01

    The fundamental framework for the criticality safety of nuclear fuel facilities regulations is, in many advanced countries, generally formulated so that technical standards or handbook data are utilized to support the licensing safety review and to implement its guidelines. In Japan also, adequacy of the safety design of nuclear fuel facilities is checked and reviewed on the basis of licensing safety review guides. These guides are, first, open-quotes The Basic Guides for Licensing Safety Review of Nuclear Fuel Facilities,close quotes and as its subsidiaries, open-quotes The Uranium Fuel Fabrication Facility Licensing Safety Review Guidesclose quotes and open-quotes The Reprocessing Facility Licensing Safety Review Guides.close quotes The open-quotes Nuclear Criticality Safety Handbook close-quote of Japan and the Technical Data Collection are published and utilized to supply related data and information for the licensing safety review, such as for the Rokkasho reprocessing plant. The well-established technical standards and data abroad such as those by the American Nuclear Society and the American National Standards Institute are also utilized to complement the standards in Japan. The basic principles of criticality safety control for nuclear fuel facilities in Japan are duly stipulated in the aforementioned basic guides as follows: 1. Guide 10: Criticality control for a single unit; 2. Guide 11: Criticality control for multiple units; 3. Guide 12: Consideration for a criticality accident

  20. Nuclear energy, today and tomorrow. Present status of development and utilization in Japan 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The world population has exceeded 5 billion, today, and it is estimated to reach 10 billion in the middle of the twenty first century. Because of such rapid increase of population, the world energy consumption is estimated to increase tremendously. Furthermore, there are problems of limited energy resources from oil and coal down, how to respond to environment problems such as global warming, acid rain caused by fossil fuel burning, followed by carbon dioxide discharge. Under such circumstances of global scale problems, the nuclear power generation that is excellent in stable nature of supply, economic advantage, less effect to the environment, supplies about 20 % of the total power generation in the world. In our country, some 30 % of the total power generation relies on the nuclear power, as an indispensable power source. Radiation utilization, together with the nuclear power generation, is an important pillar of development and utilization of nuclear energy, and has penetrated deeply in the life of the people, in the fields of industry, agriculture, medicine and environmental protection, and it is contributing to realize affluent life to a great extent. Thus, expectations to the nuclear energy seem to grow larger and larger in future. The publication introduces present status and future potential of the development and utilization of the nuclear energy in Japan, including the basic idea and concrete plans shown in the Long-Term Program. (J.P.N.)

  1. Cost estimation of hydrogen and DME produced by nuclear heat utilization system. Joint research

    International Nuclear Information System (INIS)

    Shiina, Yasuaki; Nishihara, Tetsuo

    2003-09-01

    Research of hydrogen energy has been performed in order to spread use of the hydrogen energy in 2020 or 2030. It will take, however, many years for the hydrogen energy to be used very easily like gasoline, diesel oil and city gas in all of countries. During the periods, low CO 2 release liquid fuels would be used together with hydrogen. Recently, di-methyl-either (DME) has been noticed as one of the substitute liquid fuels of petroleum. Such liquid fuels can be produced from the mixed gas such as hydrogen and carbon oxide which are produced by steam reforming hydrogen generation system by the use of nuclear heat. Therefore, the system would be one of the candidates of future system of nuclear heat utilization. In the present study, we focused on the production of hydrogen and DME. Economic evaluation was estimated for hydrogen and DME production in commercial and nuclear heat utilization plant. At first, heat and mass balance of each process in commercial plant of hydrogen production was estimated and commercial prices of each process were derived. Then, price was estimated when nuclear heat was used instead of required heat of commercial plant. Results showed that the production prices produced by nuclear heat were cheaper by 10% for hydrogen and 3% for DME. With the consideration of reduction effect of CO 2 release, utilization of nuclear heat would be more effective. (author)

  2. Chinese perceptions of the utility of nuclear weapons. Prospects and potential problems in disarmament

    Energy Technology Data Exchange (ETDEWEB)

    Jing-dong, Yuan

    2010-07-01

    deployment of the long-anticipated DF- 31 and DF-31A long-range ballistic missiles and the Jin-class ballistic missile submarines. In addition, China is also developing anti-space weapons and missile defense, as well as cruise missile capabilities. The qualitative as well as quantitative improvements of the Chinese nuclear arsenal raise important questions for the global nuclear balance in 2025 as the United States and Russia implement their nuclear disarmament commitments, further cutting down their nuclear arsenals. But the more critical question to ask is how Beijing views the utility of nuclear weapons and how and to what extent such perspectives influence China's attitudes toward and participation in multilateral nuclear disarmament. This paper begins with a detailed analysis of Chinese positions on the role of nuclear weapons and of its arms control and disarmament policies. This is followed by a preliminary discussion of Chinese responses to the nuclear-free world initiative. Finally, the paper concludes by offering some recommendations on what needs to take place to remove the obstacles and concerns that may prohibit Beijing from endorsing and participating in efforts toward eliminating nuclear weapons. (author)

  3. Chinese perceptions of the utility of nuclear weapons. Prospects and potential problems in disarmament

    International Nuclear Information System (INIS)

    Jing-dong, Yuan

    2010-01-01

    -anticipated DF- 31 and DF-31A long-range ballistic missiles and the Jin-class ballistic missile submarines. In addition, China is also developing anti-space weapons and missile defense, as well as cruise missile capabilities. The qualitative as well as quantitative improvements of the Chinese nuclear arsenal raise important questions for the global nuclear balance in 2025 as the United States and Russia implement their nuclear disarmament commitments, further cutting down their nuclear arsenals. But the more critical question to ask is how Beijing views the utility of nuclear weapons and how and to what extent such perspectives influence China's attitudes toward and participation in multilateral nuclear disarmament. This paper begins with a detailed analysis of Chinese positions on the role of nuclear weapons and of its arms control and disarmament policies. This is followed by a preliminary discussion of Chinese responses to the nuclear-free world initiative. Finally, the paper concludes by offering some recommendations on what needs to take place to remove the obstacles and concerns that may prohibit Beijing from endorsing and participating in efforts toward eliminating nuclear weapons. (author)

  4. Utility of Social Modeling in Assessment of a State's Propensity for Nuclear Proliferation

    International Nuclear Information System (INIS)

    Coles, Garill A.; Brothers, Alan J.; Whitney, Paul D.; Dalton, Angela C.; Olson, Jarrod; White, Amanda M.; Cooley, Scott K.; Youchak, Paul M.; Stafford, Samuel V.

    2011-01-01

    This report is the third and final report out of a set of three reports documenting research for the U.S. Department of Energy (DOE) National Security Administration (NASA) Office of Nonproliferation Research and Development NA-22 Simulations, Algorithms, and Modeling program that investigates how social modeling can be used to improve proliferation assessment for informing nuclear security, policy, safeguards, design of nuclear systems and research decisions. Social modeling has not to have been used to any significant extent in a proliferation studies. This report focuses on the utility of social modeling as applied to the assessment of a State's propensity to develop a nuclear weapons program.

  5. Nuclear energy and professional engineers. Possibility of utilization of professional engineer system

    International Nuclear Information System (INIS)

    Tanaka, Shunichi; Nariai, Hideki; Madarame, Haruki; Hattori, Takuya; Kitamura, Masaharu; Fujie, Takao

    2008-01-01

    Nuclear and radiation professional engineer system started in 2004 and more than 250 persons have passed the second-step professional engineer examination, while more than 1,000 persons for the first-step examination. This special issue on possibility of utilization of professional engineer system consists of six relevant articles from experts of nuclear organizations and academia. They expect the role of professional engineer in the area of nuclear energy to enhance technology advancement and awareness of professional ethics from their respective standpoints. (T. Tanaka)

  6. Development of a utility system for nuclear reaction data file: WinNRDF

    International Nuclear Information System (INIS)

    Aoyama, Shigeyoshi; Ohbayasi, Yosihide; Masui, Hiroshi; Chiba, Masaki; Kato, Kiyoshi; Ohnishi, Akira

    2000-01-01

    A utility system, WinNRDF, is developed for charged particle nuclear reaction data of NRDF (Nuclear Reaction Data File) on the Windows interface. By using this system, we can easily search the experimental data of a charged particle nuclear reaction in NRDF than old retrieval systems on the mainframe and also see graphically the experimental data on GUI (Graphical User Interface). We adopted a mechanism of making a new index of keywords to put to practical use of the time dependent properties of the NRDF database. (author)

  7. Phase-out of nuclear energy until 2022. New opportunities for public utilities?

    International Nuclear Information System (INIS)

    Herrmann, Nicolai; Praetorius, Barbara; Schilling, Jan

    2011-01-01

    In July 2011 the political leadership resolved to phase out the use of nuclear energy by the year 2022. Now the challenge is on market participants to review their corporate strategy in the light of the ramifications of this decision. This should involve not only an assessment of the development of the electricity market in general but also a company's specific ongoing and planned power plant investments. The question what opportunities and challenges the nuclear phase-out will bring in its wake is of particular significance for those public utilities which vehemently spoke against the decision taken in autumn 2010 to extend the lifetime of nuclear power plants.

  8. Utility of Social Modeling in Assessment of a State’s Propensity for Nuclear Proliferation

    Energy Technology Data Exchange (ETDEWEB)

    Coles, Garill A.; Brothers, Alan J.; Whitney, Paul D.; Dalton, Angela C.; Olson, Jarrod; White, Amanda M.; Cooley, Scott K.; Youchak, Paul M.; Stafford, Samuel V.

    2011-06-01

    This report is the third and final report out of a set of three reports documenting research for the U.S. Department of Energy (DOE) National Security Administration (NASA) Office of Nonproliferation Research and Development NA-22 Simulations, Algorithms, and Modeling program that investigates how social modeling can be used to improve proliferation assessment for informing nuclear security, policy, safeguards, design of nuclear systems and research decisions. Social modeling has not to have been used to any significant extent in a proliferation studies. This report focuses on the utility of social modeling as applied to the assessment of a State's propensity to develop a nuclear weapons program.

  9. Results of Operation and Utilization of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Luong Ba Vien; Le Vinh Vinh; Duong Van Dong; Nguyen Xuan Hai; Pham Ngoc Son; Cao Dong Vu

    2014-01-01

    The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kW was reconstructed and upgraded from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The renovated reactor was put into operation on 20 March 1984. It was designed for the purposes of radioisotope production (RI), neutron activation analysis (NAA), basic and applied researches, and nuclear education and training. During the last 30 years of operation, the DNRR was efficiently utilized for producing many kinds of radioisotopes and radiopharmaceuticals used in nuclear medicine centers and other users in industry, agriculture, hydrology and scientific research; developing a combination of nuclear analysis techniques (INAA, RNAA, PGNAA) and physic-chemical methods for quantitative analysis of about 70 elements and constituents in various samples; carrying out experiments on the reactor horizontal beam tubes for nuclear data measurement, neutron radiography and nuclear structure study; and establishing nuclear training and education programs for human resource development. This paper presents the results of operation and utilization of the DNRR. In addition, some main reactor renovation projects carried out during the last 10 years are also mentioned in the paper. (author)

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

    International Nuclear Information System (INIS)

    Shiina, Yasuaki; Nishihara, Tetsuo

    2004-09-01

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

  11. Is There Future Utility in Nuclear Weapons Nuclear Weapons Save Lives

    Science.gov (United States)

    2014-02-13

    operate with relative impunity short of large-scale conflict. Some point to a nuclear India and Pakistan as an example of instability concern. In...1997, South Asia observer Neil Joeck argued that “ India and Pakistan’s nuclear capabilities have not created strategic stability (and) do not reduce...elimination of illiteracy , provision of sustainable energy, debt relief for developing countries, clearance of landmines and more has been estimated

  12. Progress and safety aspects in process heat utilization from nuclear systems

    International Nuclear Information System (INIS)

    Barnert, H.

    1995-01-01

    Report about the Status and the Progress in the Various Programs and Projects in the Federal Republic of Germany in Process Heat Utilization from the High Temperature Reactor and on Recent Changes of the Atomic Law in the Federal Republic of Germany with Big Influence on the Safety of Nuclear Energy Technology. (author)

  13. Historical evolution of nuclear energy systems development and related activities in JAERI. Fission, fusion, accelerator utilization

    Energy Technology Data Exchange (ETDEWEB)

    Tone, Tatsuzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    Overview of the historical evolution of nuclear energy systems development and related activities in JAERI is given in the report. This report reviews the research and development for light water reactor, fast breeder reactor, high temperature gas reactor, fusion reactor and utilization of accelerator-based neutron source. (author)

  14. Fabrication of the fuel elements cladding for utilization in the fluidized bed nuclear reactor

    International Nuclear Information System (INIS)

    Schaeffer, L.; Sefidvash, F.

    1986-01-01

    A method for the fabrication of cladding of the spherical fuel elements for the utilization in the fluidized bed nuclear reactor is presented. Some prelimminary experiments were performed to adopt a method which adapt itself to mass production with the desired high quality. Still methods for cladding fabrication are under study. (Author) [pt

  15. Delays help German utilities maintain self-financing ratios. [Financing nuclear power projects

    Energy Technology Data Exchange (ETDEWEB)

    Radtke, G [Dresden Bank, AG (Germany, F.R.)

    1979-05-01

    Estimates of electricity consumption have been substantially reduced and nuclear plant is now expected to be 22% of total generating capacity in 1985 instead of the earlier forecast of 36%. The decline in the ordering of new plant has benefited the financial position of the electricity utilities and the expected fall in self-financing ratios has not occurred.

  16. Longer operating times of nuclear power plants. Options for compensating public utility advantages

    International Nuclear Information System (INIS)

    Bode, Sven; Kondziella, Hendrik; Bruckner, Thomas

    2010-01-01

    The current German government of CDU/CSU and FDP intends to prolong the operating time of existing nuclear power plants in Germany. The advantages resulting for public utilities are to be compensated. The authors discuss how compensation may be achieved and outline the available instruments. (orig.)

  17. Incentive regulation of investor-owned nuclear power plants by public utility regulators

    International Nuclear Information System (INIS)

    McKinney, M.D.; Elliot, D.B.

    1993-01-01

    The US Nuclear Regulatory Commission (NRC) periodically surveys the Federal Energy Regulatory Commission (FERC) and state regulatory commissions that regulate utility owners of nuclear power plants. The NRC is interested in identifying states that have established economic or performance incentive programs applicable to nuclear power plants, including states with new programs, how the programs are being implemented, and in determining the financial impact of the programs on the utilities. The NRC interest stems from the fact that such programs have the potential to adversely affect the safety of nuclear power plants. The information in this report was obtained from interviews conducted with each state regulatory agency that administers an incentive program and each utility that owns at least 10% of an affected nuclear power plant. The agreements, orders, and settlements that form the basis for each incentive program were reviewed as required. The interviews and supporting documentation form the basis for the individual state reports describing the structure and financial impact of each incentive program

  18. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1988

    International Nuclear Information System (INIS)

    1989-01-01

    In 1988, this system called 'Common utilization of JAERI facilities' so far was changed to 'Joint research utilizing JAERI facilities', and by evaluating more positively the function of the General Research Center for Nuclear Energy, it has been emphasized to promote and coordinate the joint research among universities centering around the utilization of JAERI facilities. The total number of the research subjects in fiscal year 1988 reached 138, but the results of 120 of them are collected in this book. General joint research is the standard form of the utilization of various facilities that JAERI has opened to common utilization. Cooperation research is to be carried out by concluding research cooperation contracts between university researchers and JAERI researchers, and the facilities which are not opened to common utilization can be used. In the general joint research, the utilization of irradiation such as activation analysis, radiochemistry, irradiation effect, neutron diffraction and so on and the research using beams are mostly carried out, but in the cooperation research, reactor engineering, reactor materials,, nuclear physics measurement and so on are the main subjects. The total number of visitors in one year was 3829 man-day. (K.I.)

  19. North American nuclear maintenance best practices compared to Japanese utility maintenance practices

    International Nuclear Information System (INIS)

    Harazim, M.L.; Ferguson, B.J.

    2003-01-01

    The purpose of this paper is to compare the best practices in North America concerning Preventive Maintenance, Predictive Maintenance and Reliability Centered Maintenance (RCM) or Preventive Maintenance Optimization (PMO) with the time-directed maintenance philosophies utilized by Japanese utilities, and how the Japanese utilities are considering (and some have begun) adopting North American ways of doing business. Preventive Maintenance Living Programs are also discussed, along with the Institute of Nuclear Power Operations AP-913 process, Equipment Reliability Process. Also, a cost benefit analysis will be demonstrated showing how major cost savings can be achieved by shifting from a predominantly time-directed maintenance philosophy to a predominantly predictive strategy utilizing vibration analysis, lubricating oil analysis, thermography and other predictive technologies to better utilize resources, reduce spare part consumption and to minimize maintenance induced errors. As a result of the strides made while incorporating these new philosophies, we no longer advocate tearing apart perfectly good equipment. (author)

  20. Anticipated development of radiation safety corresponding to utilization of nuclear technology in Vietnam

    International Nuclear Information System (INIS)

    Tran, Toan Ngoc; Le, Thiem Ngoc

    2010-01-01

    In the past, due to the limited application of radiation and radioisotope in the national economic branches, radiation safety was not paid much attention to in Vietnam. However, according to the Strategy for Peaceful Utilization of Atomic Energy up to 2020 approved by the Prime Minister on January 3, 2006 the application of radiation and radioisotopes as well as nuclear power in Vietnam is expected increasing strongly and widely, then radiation safety should be developed correspondingly. This paper presents the history of radiation protection, the current status and prospect of utilization of atomic energy and the anticipated development of the national radiation safety system to meet the demand of utilization of nuclear technology in Vietnam. (author)

  1. Proposal on nuclear information Hub in Asia. Placing stress on nuclear power utilization

    International Nuclear Information System (INIS)

    Nakasugi, Hideo

    2008-01-01

    Recently, several countries in Asia expressed official interest in nuclear power introduction toward 2020s. In designing the nuclear power introduction, estimation of required amount of resources, i.e. workload, personnel, facilities and budget corresponding to them, based upon indigenous conditions of the country, is a matter of great importance. For objective estimation, use of reliable information is indispensable, and from this point databases play essential role. However, it is not easy to reach suitable information for the purpose, due to reliability, significance, and freshness of data, and due to troublesomeness to retrieve key-words among similar data in a great quantity. For easier use, Japan Atomic Industrial Forum, Inc. (JAIF) would like to propose the information system which includes 'Asian Nuclear Information Web-Site' and 'Nuclear Information Database in Asia'. Expected participants of this system are: 1) country or area with official commitment or interest in nuclear power, and 2) organization with capacity for information provision. JAIF provisionally desires Australia, Bangladesh, China, India, Indonesia, Japan, Kazakhstan, Republic of Korea, Malaysia, Myanmar, Mongolia, Pakistan, the Philippines, Taiwan Area, Thailand, Uzbekistan, and Vietnam, for a start, to support this system. Cooperation, including publishing newsletter and holding study or symposia, could be carried out. (author)

  2. Nuclear energy policy analysis under uncertainties : applications of new utility theoretic approaches

    International Nuclear Information System (INIS)

    Ra, Ki Yong

    1992-02-01

    For the purpose of analyzing the nuclear energy policy under uncertainties, new utility theoretic approaches were applied. The main discoveries of new utility theories are that, firstly, the consequences can affect the perceived probabilities, secondly, the utilities are not fixed but can change, and finally, utilities and probabilities thus should be combined dependently to determine the overall worth of risky option. These conclusions were applied to develop the modified expected utility model and to establish the probabilistic nuclear safety criterion. The modified expected utility model was developed in order to resolve the inconsistencies between the expected utility model and the actual decision behaviors. Based on information theory and Bayesian inference, the modified probabilities were obtained as the stated probabilities times substitutional factors. The model theoretically predicts that the extreme value outcomes are perceived as to be more likely to occur than medium value outcomes. This prediction is consistent with the first finding of new utility theories that the consequences can after the perceived probabilities. And further with this theoretical prediction, the decision behavior of buying lottery ticket, of paying for insurance and of nuclear catastrophic risk aversion can well be explained. Through the numerical application, it is shown that the developed model can well explain the common consequence effect, common ratio effect and reflection effect. The probabilistic nuclear safety criterion for core melt frequency was established: Firstly, the distribution of the public's safety goal (DPSG) was proposed for representing the public's group preference under risk. Secondly, a new probabilistic safety criterion (PSC) was established, in which the DPSG was used as a benchmark for evaluating the results of probabilistic safety assessment. Thirdly, a log-normal distribution was proposed as the appropriate DPSG for core melt frequency using the

  3. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2

    International Nuclear Information System (INIS)

    Osborn, R.N.; Olson, J.; Sommers, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators

  4. The comparison of alternatives for nuclear spent fuel management using multi-attribute utility function

    International Nuclear Information System (INIS)

    Yang, J. W.; Kang, C. S.

    1999-01-01

    It is necessary to find a solution immediately to nuclear spent fuel management that is temporarily stored in on-site spent fuel storage before the saturation of the storage. However the choice of alternative for nuclear spent fuel management consists of complex process that are affected by economic, technical and social factors. And it is not easy to quantify these factors; public opinion, probability of diplomatic problem and contribution to development of nuclear technology. Therefore the analysis of the affecting factors and assessment of alternatives are required. This study performed the comparison of the alternatives for nuclear spent fuel management using MAU (Multi-Attribute Utility Function) and AHP(Analytic Hierarchy Process)

  5. Utilization of a full-scope simulation for training the operating personel of nuclear power plants

    International Nuclear Information System (INIS)

    Mathias, S.G.

    1987-01-01

    A full-scope simulator of the Angra-2 Nuclear Power Plant has been installed at the NUCLEBRAS Training Center in Mambucaba - close to the site where that Plant is being built -, the goal of providing training for the operating personnel of the KWU-design nuclear power plants to be installed in Brazil. Due to the delays which occurred in the construction of Angra-2, NUCLEBRAS has established an extensive program for the utilization of the simulator for the training of operators for German nuclear power plants and for Spain's Trillo Plant. Besides yielding profits to NUCLEBRAS, that program is resulting in considerable experience in the area of nuclear power plant operators' training generating international recognition to the NUCLEBRAS Training Center. (Author) [pt

  6. The safety of nuclear power plants under the shareholder value orientation - example Northeast Utilities

    International Nuclear Information System (INIS)

    Luhmann, H.J.

    2006-01-01

    Usually the safety of nuclear power plants is regarded as a technical question. Thereby humans only as a part of the man-machine system play a safety-relevant role usually. On this picture, the national regulation of this safety, the 'nuclear supervision' is designed. An innovative investigation of the Yale School of Management has concerned with the incidents around the so-called Millstone reactors in Waterford, Connecticut, and the economic collapse of the regional supplier Northeast Utilities (NU). The change of the corporate culture of the operator of the nuclear power station to a shareholder value orientation has released this 'enterprise disaster'. This investigation permits a first insight into the changed requirements on supervision, which goes beyond the nuclear supervision and which includes the price control in view of this change of the corporate culture

  7. Statistical utility theory for comparison of nuclear versus fossil power plant alternatives

    International Nuclear Information System (INIS)

    Garribba, S.; Ovi, A.

    1977-01-01

    A statistical formulation of utility theory is developed for decision problems concerned with the choice among alternative strategies in electric energy production. Four alternatives are considered: nuclear power, fossil power, solar energy, and conservation policy. Attention is focused on a public electric utility thought of as a rational decision-maker. A framework for decisions is then suggested where the admissible strategies and their possible consequences represent the information available to the decision-maker. Once the objectives of the decision process are assessed, consequences can be quantified in terms of measures of effectiveness. Maximum expected utility is the criterion of choice among alternatives. Steps toward expected values are the evaluation of the multidimensional utility function and the assessment of subjective probabilities for consequences. In this respect, the multiplicative form of the utility function seems less restrictive than the additive form and almost as manageable to implement. Probabilities are expressed through subjective marginal probability density functions given at a discrete number of points. The final stage of the decision model is to establish the value of each strategy. To this scope, expected utilities are computed and scaled. The result is that nuclear power offers the best alternative. 8 figures, 9 tables, 32 references

  8. High degree utilization of computers for design of nuclear power plants

    International Nuclear Information System (INIS)

    Masui, Takao; Sawada, Takashi

    1992-01-01

    Nuclear power plants are the huge technology in which various technologies are compounded, and the high safety is demanded. Therefore, in the design of nuclear power plants, it is necessary to carry out the design by sufficiently grasping the behavior of the plants, and to confirm the safety by carrying out the accurate design evaluation supposing the various operational conditions, and as the indispensable tool for these analysis and evaluation, the most advanced computers in that age have been utilized. As to the utilization for the design, there are the fields of design, analysis and evaluation and another fields of the application to the support of design. Also in the field of the application to operation control, computers are utilized. The utilization of computers for the core design, hydrothermal design, core structure design, safety analysis and structural analysis of PWR plants, and for the nuclear design, safety analysis and heat flow analysis of FBR plants, the application to the support of design and the application to operation control are explained. (K.I.)

  9. Utilization technique for advanced nuclear materials database system Data-Free-Way'

    International Nuclear Information System (INIS)

    Fujita, Mitsutane; Kurihara, Yutaka; Kinugawa, Junichi; Kitajima, Masahiro; Nagakawa, Josei; Yamamoto, Norikazu; Noda, Tetsuji; Yagi, Koichi; Ono, Akira

    2001-01-01

    Four organizations the National Research Institute for Metals (NRIM), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Fuel Cycle Development Institute (JNC) and Japan Science and Technology Incorporation (JST), conducted the 2nd period joint research for the purpose of development of utilization techniques for advanced nuclear materials database system named 'Data-Free-Way' (DFW), to make more useful system to support research and development of the nuclear materials, from FY 1995 to FY 1999. NRIM intended to fill a data system on diffusion and nuclear data by developing utilization technique on diffusion informations of steels and aluminum and nuclear data for materials for its independent system together with participating in fulfil of the DFW. And, NRIM has entered to a project on wide area band circuit application agreed at the G7 by using technologies cultivated by NRIM, to investigate network application technology with the Michigan State University over the sea under cooperation assistant business of JST, to make results on CCT diagram for welding and forecasting of welding heat history accumulated at NRIM for a long term, to perform development of a simulator assisting optimum condition decision of welding. (G.K.)

  10. Utilization technique for advanced nuclear materials database system Data-Free-Way'

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Mitsutane; Kurihara, Yutaka; Kinugawa, Junichi; Kitajima, Masahiro; Nagakawa, Josei; Yamamoto, Norikazu; Noda, Tetsuji; Yagi, Koichi; Ono, Akira [National Research Inst. for Metals, Tsukuba, Ibaraki (Japan)

    2001-02-01

    Four organizations the National Research Institute for Metals (NRIM), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Fuel Cycle Development Institute (JNC) and Japan Science and Technology Incorporation (JST), conducted the 2nd period joint research for the purpose of development of utilization techniques for advanced nuclear materials database system named 'Data-Free-Way' (DFW), to make more useful system to support research and development of the nuclear materials, from FY 1995 to FY 1999. NRIM intended to fill a data system on diffusion and nuclear data by developing utilization technique on diffusion informations of steels and aluminum and nuclear data for materials for its independent system together with participating in fulfil of the DFW. And, NRIM has entered to a project on wide area band circuit application agreed at the G7 by using technologies cultivated by NRIM, to investigate network application technology with the Michigan State University over the sea under cooperation assistant business of JST, to make results on CCT diagram for welding and forecasting of welding heat history accumulated at NRIM for a long term, to perform development of a simulator assisting optimum condition decision of welding. (G.K.)

  11. A Study on Guidelines for the Utilization of Unproven MMIS Technology In Nuclear Power Plant Application

    International Nuclear Information System (INIS)

    Kang, Sung Kon; Shin, Yeong Cheol; Bae, Byoung Hwan

    2007-01-01

    New MMIS (Man Machine Interface System) technology is rapidly advanced as digital technology provides opportunity for more functionality and better cost effectiveness and NPP (Nuclear Power Plant) operators are inclined to use the new technology for the construction of new plant and for the upgrade of existing plants. However, this new technology poses risks to the NPP operators at the same time. These risks are mainly due to the poor reliability of newly developed technology. KHNP's past experiences with the new MMIS equipment shows many cases of reliability problem. And their consequences include unintended plant trips, lowered acceptance of the new digital technology by the plant I and C maintenance crew, and increased licensing burden in answering for questions from the nuclear regulatory body. Considering the fact that the risk of these failures in the nuclear plant operation is far greater than those in other industry, utilities require proven technology for the MMIS in nuclear power plants. So that new MMIS technology might be testified as proven technology, guidelines for the utilization of unproven MMIS technology in nuclear power plant application is required for applying new advanced MMIS technology which is apparently needed to obtain a definite gain in simplicity or performance

  12. The Utilization of Dalat nuclear research reactor for education and training purposes

    International Nuclear Information System (INIS)

    Luong, Ba Vien; Nguyen, Nhi Dien; Le, Vinh Vinh; Nguyen, Xuan Hai

    2017-01-01

    The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kWt is today the unique one in Vietnam. It was designed for the purposes of radioisotope production, neutron activation analysis, basic and applied researches, and nuclear education and training. With the rising demand in development of human resources for utilization of atomic energy in the country, the DNRR has been playing an important role in the nuclear education and training for students from universities and professionals who are interested in reactor engineering. At present, the Dalat Nuclear Research Institute (DNRI) offers two types of training course utilizing the research reactor: an one-week practical training course is applied for undergraduate students and a two-week training course on reactor engineering is applied for the professionals. This paper presents the reactor facility and experiments performed at the DNRR for education and training purposes. In addition, the co-operation between the DNRI with national and international educational organizations for nuclear human resource development for national and regional demands is also mentioned in the paper. (author)

  13. Utilization of water soluble plastics for radiological control within nuclear power plants

    International Nuclear Information System (INIS)

    Smith, R.J.; Deltete, C.P.; Homyk, W.A.; Kasprzak, L.; Robinson, P.J.

    1989-01-01

    The utilization of plastic products for radioactive contamination control within nuclear power facilities currently results in relatively large volumes of waste requiring disposal as low-level radioactive waste. The utilization of a polymer resin product that possesses comparable physical attributes to currently utilized plastic materials, but which is water soluble, has significant potential to reduce the volume of plastic waste requiring disposal as radwaste. Such a volume reduction will reduce overall plant )ampersand M costs, reduce the overall waste volume allocation utilization, and improve the regulatory perception of any plant realizing a volume reduction through plastic source minimization. This potential reduction in waste volume (and associated availability of the Low-level Waste Policy Amendments Act disposal allocation for other purposes), combined with potential economic benefits summarized above, has led to the undertaking of a detailed evaluation, presented in this paper

  14. Development of utility system of charged particle Nuclear Reaction Data on Unified Interface

    International Nuclear Information System (INIS)

    Aoyama, Shigeyoshi; Ohbayashi, Yosihide; Kato, Kiyoshi; Masui, Hiroshi; Ohnishi, Akira; Chiba, Masaki

    1999-01-01

    We have developed a utility system, WinNRDF, for a nuclear charged particle reaction data of NRDF (Nuclear Reaction Data File) on a unified interface of Windows95, 98/NT. By using the system, we can easily search the experimental data of a charged particle reaction in NRDF and also see the graphic data on GUI (Graphical User Interface). Furthermore, we develop a mechanism of making a new index of keywords in order to include the time developing character of the NRDF database. (author)

  15. Current status and future prospects of nuclear energy utilization in Japan

    International Nuclear Information System (INIS)

    Kondo, S.

    2006-01-01

    Nuclear power is recognized as a safe, reliable and competitive energy source in Japan as Japan's 55 nuclear power plants supply about a third of the country's electricity and contribute to the rise in her degree of self-sufficiency in primary energy supply from 4% to 17%. It is also a practical and effective mean to observe the promise of the Kyoto Protocol to reduce CO2 emissions into atmosphere. The development of nuclear science and engineering, on the other hand, contributes not only to the advancement of science and technology in various fields but also to the improvement of health and living standards of the people as well as to the industrial prosperity through the application of radiation to medical diagnosis, cancer treatment, insect pest control, production of semi-conductors, radial tiers, etc. Major goal of current nuclear energy policy in Japan is to enrich the basic measures that compose the basis for the utilization of nuclear energy technologies in civil society and encourage academia and industries to innovate themselves to grapple the challenge, while sustaining the share of nuclear power in electricity generation after the year 2030 at the level equal to or greater than the current level of 30-40% based on the strategy to recycle uranium and plutonium from nuclear spent fuels, in addition to the expansion of the use of radiation technologies. Major policy areas are the improvement of institutional and financial arrangements to promote safe and effective utilization of nuclear energy technology including radiation technologies, the promotion of effective and efficient research and development activities, and the promotion of bilateral and multilateral cooperative activities necessary and or useful for facilitating these activities, in addition to nurturing the international political and institutional environment suitable for the sound promotion of nuclear energy utilization in the world. To pursue these goals, Japanese government and industries

  16. Descriptive statistics of occupational employment in nuclear power utilities. Final working paper

    International Nuclear Information System (INIS)

    Little, J.R.; Johnson, R.C.

    1982-10-01

    The Institute of Nuclear Power Operations conducted a survey of its 58 member utilities during the Spring of 1982. This was the second such survey performed to identify employment trends and to project needs for trained personnel in the industry to 1991. The first was performed in 1981. The 1982 employment survey consisted of four questionnaires, asking for information on: (1) on-site employment; (2) on-site turnover; (3) off-site employment; and (4) off-site turnover. The survey instruments were designed to reflect approaches used by the utilities to meet the labor requirements for operation of nuclear power plants through off-site support personnel, contractors, and holding company personnel, as well as utility employees working at the plant site. On-site information was received from all 83 plants at the 58 utilities. However, employment information from Surry of VEPCO arrived too late to be included in the analysis. Therefore, their numbers are reflected in the adjusted totals. Responses to requests for off-site employment information were received from 55 of the 58 utilities

  17. Nuclear R+D+I in Spanish utilities. Programs and strategies

    International Nuclear Information System (INIS)

    Farmacia, L.; Casero, M.

    2003-01-01

    The Spanish Utilities have traditionally devoted important resources to Research. Development and Innovation in the nuclear field in order to improve the technology and the tools needed for its proper management, as well as to increase the knowledge on the phenomena associated to a safe and reliable operation of the Spanish NPPs. The purpose of this article is to show the continuous effort of the Spanish Utilities to get that the research results better meet the NPPs needs, to improve the coordination with other national and international agents with the aim of ensuring an optimum use of the resources and capabilities, and, most of all, to permanently incorporate the lessons learned. (Author)

  18. Status report of the program on neutron beam utilization at the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Vuong Huu Tan

    1996-08-01

    The thermal reactor is an intense source not only of thermal neutron, but also intermediate as well as fast neutrons. Using the filtered neutron beam technique at steady state atomic reactor allows receiving the neutrons in the intermediate energy region with the most available intense flux at present. In the near time at the Dalat reactor the filtered neutron beam technique has been applied. Utilization of the filtered neutron beams in basic and applied researches has been a important activity of the Dalat Nuclear Research Institute (DNRI). This report presents some relevant characteristics of the filtered neutron beams and their utilization in nuclear data measurements, neutron capture gamma ray spectroscopy, neutron radiography, neutron dose calibration and other applications. (author). 3 refs, 2 figs

  19. Training and qualification of licensed reactor operators at General Public Utilities Nuclear Corporation

    International Nuclear Information System (INIS)

    Long, R.L.; Coe, R.P.

    1992-01-01

    Following the Three Mile Island-2 (TMI-2) accident in 1979, the utility responsible for managing the facility has looked closely at the training and qualification of its reactor operators. Performance-based operator training programmes are now in place, as required by the United States National Academy for Nuclear Training. Operators also participate directly in the development of a professional code of behaviour. (UK)

  20. Geochronology and geochemistry by nuclear tracks method: some utilization examples in geologic applied

    International Nuclear Information System (INIS)

    Poupeau, G.; Soliani Junior, E.

    1988-01-01

    This article discuss some applications of the 'nuclear tracks method' in geochronology, geochemistry and geophysic. In geochronology, after rapid presentation of the dating principles by 'Fission Track' and the kinds of geological events mensurable by this method, is showed some application in metallogeny and in petroleum geolocy. In geochemistry the 'fission tracks' method utilizations are related with mining prospecting and uranium prospecting. In geophysics an important application is the earthquake prevision, through the Ra 222 emanations continous control. (author) [pt

  1. Nuclear Safety R and D Programs and trend in the U. S. Utility Industry

    International Nuclear Information System (INIS)

    Kim, Jong Hyun

    1992-01-01

    First of all, the deterministic approach to safety analysis, which had dominated safety research in the earlier years, has given much ground to probabilistic approach. Secondly, human factors analysis has become an important part of safety research. Third, safety research relevant to reliability, or safety combined with reliability, are gradually taking place of purely safety-oriented or stand-alone safety research. More and more nuclear utilities in the U. S. are integrating safety with reliability. This evolution is in part due to the successful completion of major safety testing and analyses of deterministic nature, and partially due to the utility industry's desire to harvest synergistic nature, and partially due to the utility industry's desire to harvest synergistic results by combining safety with reliability, as the utility industry is more and more concerned about reducing operation and maintenance costs by enhancing reliability while maintaining plant safety. Nuclear safety is a complex and comprehensive concept, defying a simple categorization or interpretation. Thus, research and development in nuclear safety is necessarily diverse, and the program areas and trend presented in this paper are not meant to be all inclusive. For instance, there are some other active areas that were not mentioned, such as seismic risk assessment program and others. Nuclear safety research and development activities have undergone a perceptible shift of emphasis in recent years. They have become more focused and product-oriented. Also, except for the severe accident analysis, the emphasis on prevention and mitigation of accident, rather than analyzing the consequences of accident, is very much in evidence; that is, reliability-based technologies using PIRA methodology, and upgrading of instrumentation and control technologies are in the main stream of activities

  2. The role of nuclear energy in reducing the environmental impact of China's energy utilization

    International Nuclear Information System (INIS)

    Wu, Zongxin; Sun, Yuliang

    1998-01-01

    It is presented in this paper the current status of China's energy market and the projections of its future development. China's energy market, currently and in the next decades, is mainly characterized by rapidly increasing demand and dominant role of coal which is directly related to serious environmental pollution. The role of nuclear energy utilization in improving the primary energy infrastructure is addressed. Status and development of nuclear power generation are described. Potential of introducing nuclear energy into heat market is discussed. An overview of the research and development work of water cooled low temperature heating reactors and gas-cooled high temperature gas cooled reactors in China is given and the technical and safety features of these two reactor types are briefly described. (author)

  3. Nuclear new-build - Status and Outlook from a German utility perspective

    International Nuclear Information System (INIS)

    Koenig, Ruediger; Lefhalm, Cord-H.

    2009-01-01

    Full text: As one of the Top 5 utilities in Europe, Rheinisch-Westfaelisches Elektrizitaetswerk AG, FWB: RW, RWE, operates a diversified generating capacity of about 45 GW; RWE Power alone generates over 30 GW. Besides a share of approximately 20% nuclear power, a large proportion of the generating base is in lignite and hard coal. RWE has an ambitious, Euro10 bn newbuild program of about 10 GW modern fossil fired plants and further expansion plans across Europe. By 2012, RWE intends to invest between Euro 15 and 20 bn outside Germany.The European Union has a challenging policy to increase the share of renewables, improve energy efficiency, and reduce greenhouse gases by 2020. At the same time, ageing power plants need to be replaced. This requires an enormous investment program across Europe. Nuclear power therefore, as a proven technology with low lifecycle carbon emissions and reasonable lifecycle cost, is a crucial contributor to achieve Europe's 2020 goals. Accordingly, most European countries have started or are planning to expand their nuclear generating base by lifetime extension, capacity upgrades, and newbuild projects. Germany is one of the few countries where the Government has not yet adopted a pro-nuclear policy. Instead, the law of the land still forces early plant closures. Against this background, RWE is determined to reduce its CO 2 exposure and grow internationally; work towards preserving nuclear energy in Germany; expand its nuclear energy-based generation portfolio in other markets, especially UK and CSEE. As a pioneer in the civilian nuclear industry, RWE can build on a wealth of experience for engaging in new nuclear projects. We have established a set of strict guidelines with which we evaluate project opportunities, starting with the fundamental requirement that, beyond any regulatory requirements, safety must be guaranteed according to RWE's high standards. On this basis, RWE has been successfully able to engage in two of the first

  4. Efficacy of clinical diagnostic procedures utilized in nuclear medicine. Nine month progress report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    This study is designed to determine the efficacy of nuclear medicine procedures in clinical practice. Several methods of determining efficacy will be evaluated to determine those most suitable. Nuclear medicine methods will be confined to the study of lung diseases by pulmonary perfusion and ventilation. In addition to evaluating the above methods data will be obtained to determine the sensitivity, specificity, predictive value and efficiency of the test under consideration. These values, corrected for prevalence of the disease processes under consideration will then be compared to the values obtained by the MACRO and MICRO methods and will help to bound the clinical reliability of the diagnostic method depending on the degree to which the several methods trend together. Depending on the practicality of these two methods, in addition to the determination of efficacy, cost effectiveness factors and benefit-risk estimates which are used to apply to radiation effects will be determined for nuclear medicine studies of the brain, bone, heart, liver and thyroid subsequently. The measurement techniques will then be utilized to establish guidelines for the most useful applications of the given procedure so that clinicians will be able to obtain a pretest estimate of the utility of the nuclear medicine test.

  5. Government, utilities, industry and universities: partners for nuclear development in Canada and abroad

    International Nuclear Information System (INIS)

    Hurst, D.G.; Woolston, J.E.

    1971-09-01

    In Canada, eleven power reactors installed or committed at four sites will provide 5 520 MW(e) for an investment of $1 800 million. Uranium production during the decade 1958-1967 totalled 79 700 tonnes U 3 O 8 worth $1 621 million. For nuclear research, development and control, the federal government employs about 6 000 people and spends about $80 million/year which includes the cost of operating three major research reactors (> 30 MW each). Aggregate commercial isotope production has reached 14 megacuries, and Canada has about 3 000 licensed users. Three power and two research reactors of Canadian design are or will be installed in developing countries overseas. Legislation in 1946 made atomic energy a federal responsibility and established an Atomic Energy Control Board. The Board's regulations, which deal primarily with health, safety and security, are administered with the co-operation of appropriate departments of the federal and provincial governments. Large-scale nuclear research began in 1941 and continued under the National Research Council until 1952 when the federal government created a public corporation, Atomic Energy of Canada Limited, to take over both research and the exploitation of atomic energy. Another public corporation, Eldorado Nuclear Limited, conducts research and development on the processing of uranium and operates Canada's only uranium refinery, but prospecting and mining is undertaken largely by private companies. The publicly owned electrical utilities of Ontario and Quebec operate nuclear power stations and participate, with governments, in their financing. Private industry undertakes extensive development and manufacturing, mainly under contract to Atomic Energy of Canada Limited and the utilities, and industry has formed its own Canadian Nuclear Association. Canadian universities undertake nuclear research, and receive significant government support; one has operated a research reactor since 1959. Canada's nuclear program is

  6. Influenza polymerase encoding mRNAs utilize atypical mRNA nuclear export.

    Science.gov (United States)

    Larsen, Sean; Bui, Steven; Perez, Veronica; Mohammad, Adeba; Medina-Ramirez, Hilario; Newcomb, Laura L

    2014-08-28

    Influenza is a segmented negative strand RNA virus. Each RNA segment is encapsulated by influenza nucleoprotein and bound by the viral RNA dependent RNA polymerase (RdRP) to form viral ribonucleoproteins responsible for RNA synthesis in the nucleus of the host cell. Influenza transcription results in spliced mRNAs (M2 and NS2), intron-containing mRNAs (M1 and NS1), and intron-less mRNAs (HA, NA, NP, PB1, PB2, and PA), all of which undergo nuclear export into the cytoplasm for translation. Most cellular mRNA nuclear export is Nxf1-mediated, while select mRNAs utilize Crm1. Here we inhibited Nxf1 and Crm1 nuclear export prior to infection with influenza A/Udorn/307/1972(H3N2) virus and analyzed influenza intron-less mRNAs using cellular fractionation and reverse transcription-quantitative polymerase chain reaction (RT-qPCR). We examined direct interaction between Nxf1 and influenza intron-less mRNAs using immuno purification of Nxf1 and RT-PCR of associated RNA. Inhibition of Nxf1 resulted in less influenza intron-less mRNA export into the cytoplasm for HA and NA influenza mRNAs in both human embryonic kidney cell line (293 T) and human lung adenocarcinoma epithelial cell line (A549). However, in 293 T cells no change was observed for mRNAs encoding the components of the viral ribonucleoproteins; NP, PA, PB1, and PB2, while in A549 cells, only PA, PB1, and PB2 mRNAs, encoding the RdRP, remained unaffected; NP mRNA was reduced in the cytoplasm. In A549 cells NP, NA, HA, mRNAs were found associated with Nxf1 but PA, PB1, and PB2 mRNAs were not. Crm1 inhibition also resulted in no significant difference in PA, PB1, and PB2 mRNA nuclear export. These results further confirm Nxf1-mediated nuclear export is functional during the influenza life cycle and hijacked for select influenza mRNA nuclear export. We reveal a cell type difference for Nxf1-mediated nuclear export of influenza NP mRNA, a reminder that cell type can influence molecular mechanisms. Importantly, we

  7. Innovative nuclear thermal rocket concept utilizing LEU fuel for space application

    International Nuclear Information System (INIS)

    Nam, Seung Hyun; Venneri, Paolo; Choi, Jae Young; Jeong, Yong Hoon; Chang, Soon Heung

    2015-01-01

    Space is one of the best places for humanity to turn to keep learning and exploiting. A Nuclear Thermal Rocket (NTR) is a viable and more efficient option for human space exploration than the existing Chemical Rockets (CRs) which are highly inefficient for long-term manned missions such as to Mars and its satellites. NERVA derived NTR engines have been studied for the human missions as a mainstream in the United States of America (USA). Actually, the NERVA technology has already been developed and successfully tested since 1950s. The state-of-the-art technology is based on a Hydrogen gas (H_2) cooled high temperature reactor with solid core utilizing High-Enriched Uranium (HEU) fuel to reduce heavy metal mass and to use fast or epithermal neutron spectrums enabling simple core designs. However, even though the NTR designs utilizing HEU is the best option in terms of rocket performance, they inevitably provoke nuclear proliferation obstacles on all Research and Development (R and D) activities by civilians and non-nuclear weapon states, and its eventual commercialization. To surmount the security issue to use HEU fuel for a NTR, a concept of the innovative NTR engine, Korea Advanced NUclear Thermal Engine Rocket utilizing Low-Enriched Uranium fuel (KANUTER-LEU) is presented in this paper. The design goal of KANUTER-LEU is to make use of a LEU fuel for its compact reactor, but does not sacrifice the rocket performance relative to the traditional NTRs utilizing HEU. KANUTER-LEU mainly consists of a fission reactor utilizing H_2 propellant, a propulsion system and an optional Electricity Generation System as a bimodal engine. To implement LEU fuel for the reactor, the innovative engine adopts W-UO_2 CERMET fuel to drastically increase uranium density and thermal neutron spectrum to improve neutron economy in the core. The moderator and structural material selections also consider neutronic and thermo-physical characteristics to reduce non-fission neutron loss and

  8. Nuclear energy development and utilization in the republic of Korea and desirable policy directions

    International Nuclear Information System (INIS)

    Yoon, Youngku; Chang, Soon Heung

    1994-01-01

    There have been important worldwide changes in recent years that will have great influence on out future. The collapse of the former Soviet Union and East Europe and the final agreements of the Uruguay Round (UR) indicate that the world's future focus lies on economics and technology rather than ideology. Each nation is trying to strengthen its international competitiveness, and thereby maximize their national interests in this age of limitless competition. The worldwide energy consumption, especially in developing countries, is expected to increase continuously in the next century. Considering the limited resources of fossil fuels, securing a stable energy supply will be a factor of paramount importance from the viewpoint of national security. Another important problem of mankind in the 21th century is to preserve the environment of the earth, while maintaining economic growth. Recognition of the importance of the earth environment is spreading very rapidly, especially in advanced countries. Concrete approaches to preserve the earth environment are expected to be formulated in the upcoming Green Round (GR) negotiations which follow the UR. Probably the GR will demand an overall reorganization of the industrial structure. With respect to nuclear energy, the threat of nuclear weapons of the former Soviet union has significantly lessened owing to the termination of the Cold War. However, international regulations for nuclear non-proliferation are being strengthened as the countermeasure for the deterioration of management and surveillance capability of the former Soviet Union for nuclear weapons and for the increase in the possibility of nuclear weapons development in Iraq, North Korea, etc. Domestically, the Declaration of Denuclearization of the Korean Peninsula, the possibility of North Korea's disregard of the NPT, and the opposition of local people to construction of nuclear facilities have caused significant difficulties in efficient development and utilization

  9. Nuclear energy development and utilization in the republic of Korea and desirable policy directions

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Youngku; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1994-04-15

    There have been important worldwide changes in recent years that will have great influence on out future. The collapse of the former Soviet Union and East Europe and the final agreements of the Uruguay Round (UR) indicate that the world's future focus lies on economics and technology rather than ideology. Each nation is trying to strengthen its international competitiveness, and thereby maximize their national interests in this age of limitless competition. The worldwide energy consumption, especially in developing countries, is expected to increase continuously in the next century. Considering the limited resources of fossil fuels, securing a stable energy supply will be a factor of paramount importance from the viewpoint of national security. Another important problem of mankind in the 21th century is to preserve the environment of the earth, while maintaining economic growth. Recognition of the importance of the earth environment is spreading very rapidly, especially in advanced countries. Concrete approaches to preserve the earth environment are expected to be formulated in the upcoming Green Round (GR) negotiations which follow the UR. Probably the GR will demand an overall reorganization of the industrial structure. With respect to nuclear energy, the threat of nuclear weapons of the former Soviet union has significantly lessened owing to the termination of the Cold War. However, international regulations for nuclear non-proliferation are being strengthened as the countermeasure for the deterioration of management and surveillance capability of the former Soviet Union for nuclear weapons and for the increase in the possibility of nuclear weapons development in Iraq, North Korea, etc. Domestically, the Declaration of Denuclearization of the Korean Peninsula, the possibility of North Korea's disregard of the NPT, and the opposition of local people to construction of nuclear facilities have caused significant difficulties in efficient development and utilization

  10. Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 2

    International Nuclear Information System (INIS)

    1983-08-01

    Nuclear wastes from the defense production cycle contain many uniquely useful, intrinsically valuable, and strategically important materials. These materials have a wide range of known and potential applications in food technology, agriculture, energy, public health, medicine, industrial technology, and national security. Furthermore, their removal from the nuclear waste stream can facilitate waste management and yield economic, safety, and environmental advantages in the management and disposal of the residual nuclear wastes that have no redemptive value. This document is the program plan for implementing the recovery and beneficial use of these valuable materials. An Executive Summary of this document, DOE/DP-0013, Vol. 1, January 1983, is available. Program policy, goals and strategy are stated in Section 2. Implementation tasks, schedule and funding are detailed in Section 3. The remaining five sections and the appendixes provide necessary background information to support these two sections. Section 4 reviews some of the unique properties of the individual byproduct materials and describes both demonstrated and potential applications. The amounts of byproduct materials that are available now for research and demonstration purposes, and the amounts that could be recovered in the future for expanded applications are detailed in Section 5. Section 6 describes the effects byproduct recovery and utilization have on the management and final disposal of nuclear wastes. The institutional issues that affect the recovery, processing and utilization of nuclear byproducts are discussed in Section 7. Finally, Section 8 presents a generalized mathematical process by which applications can be evaluated and prioritized (rank-ordered) to provide planning data for program management

  11. Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1983-08-01

    Nuclear wastes from the defense production cycle contain many uniquely useful, intrinsically valuable, and strategically important materials. These materials have a wide range of known and potential applications in food technology, agriculture, energy, public health, medicine, industrial technology, and national security. Furthermore, their removal from the nuclear waste stream can facilitate waste management and yield economic, safety, and environmental advantages in the management and disposal of the residual nuclear wastes that have no redemptive value. This document is the program plan for implementing the recovery and beneficial use of these valuable materials. An Executive Summary of this document, DOE/DP-0013, Vol. 1, January 1983, is available. Program policy, goals and strategy are stated in Section 2. Implementation tasks, schedule and funding are detailed in Section 3. The remaining five sections and the appendixes provide necessary background information to support these two sections. Section 4 reviews some of the unique properties of the individual byproduct materials and describes both demonstrated and potential applications. The amounts of byproduct materials that are available now for research and demonstration purposes, and the amounts that could be recovered in the future for expanded applications are detailed in Section 5. Section 6 describes the effects byproduct recovery and utilization have on the management and final disposal of nuclear wastes. The institutional issues that affect the recovery, processing and utilization of nuclear byproducts are discussed in Section 7. Finally, Section 8 presents a generalized mathematical process by which applications can be evaluated and prioritized (rank-ordered) to provide planning data for program management.

  12. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1984

    International Nuclear Information System (INIS)

    Sotic, O.; Martinc, R.; Cupac, S.; Sulem, B.; Badrljica, R.; Majstorovic, D.; Sanovic, V.

    1984-12-01

    During the 1984 the reactor operation was limited by the temporary operating license issued by the Committee of Serbian ministry for health and social care. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. This temporary license has limited the reactor power to 2 MW from 1981. Operation of the primary cooling system was changed in order to avoid appearance of the previously noticed aluminium oxyhydrate on the surface of the fuel element claddings. The new cooling regime enabled more efficient heavy water purification. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1984, three major tasks are planned: building of the new emergency system, reconstruction of the existing ventilation system, and renewal of the reactor instrumentation. Financing of the planned activities will be partly covered by the IAEA. this Part I of the report includes 8 Annexes describing in detail the reactor operation, and 6 special papers dealing with the problems of reactor operation and utilization

  13. Best practices in the utilization and dissemination of operating experience at nuclear power plants

    International Nuclear Information System (INIS)

    2008-03-01

    IAEA Safety Standards Series No. SF-1 entitled Fundamental Safety Principles: Safety Fundamentals states the need for operating organizations to establish a programme for the collection and analysis of operating experience in nuclear power plants. Such a programme ensures that operating experience is analysed, events important to safety are reviewed in depth, lessons learned are disseminated to the staff of the organization and to relevant national and international organizations, operating experience is utilized and corrective actions are effectively implemented. This publication has been developed to provide advice and assistance to nuclear installations and related institutions, including contractors and support organizations, to strengthen and enhance their own feedback process through the implementation of best practices in the utilization and dissemination of operating experience and to assess their effectiveness. Dissemination and utilization of internal and external operating experience is essential in supporting a proactive safety management approach of preventing events from occurring. Few new events reveal a completely new cause or failure mechanism. Although not recognized prior to the event, most subsequent investigations identify internal or external industry operating experience that, if applied effectively, would have prevented the event. Therefore, the establishment of an effective utilization and dissemination process is very beneficial in raising awareness of the organization and individuals of available operating experience, and focussing effort in the implementation of the lessons learnt. This leads to improved safety and reliability. The present publication is the outcome of a coordinated effort involving the participation of experts of nuclear organizations in several Member States. It was written to complement the publication IAEA Services Series No. 10 entitled PROSPER Guidelines - Guidelines for Peer Review and for Plant Self-assessment of

  14. A technology-assessment methodology for electric utility planning: With application to nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Lough, W.T.

    1987-01-01

    Electric utilities and public service commissions have not taken full advantage of the many proven methodologies and techniques available for evaluating complex technological issues. In addition, evaluations performed are deficient in their use of (1) methods for evaluating public attitudes and (2) formal methods of analysis for decision making. These oversight are substantiated through an examination of the literature relevant to electric utility planning. The assessment process known as technology assessment or TA is proposed, and a TA model is developed for route in use in utility planning by electric utilities and state regulatory commissions. Techniques to facilitate public participation and techniques to aid decision making are integral to the proposed model and are described in detail. Criteria are provided for selecting an appropriate technique on a case-by-case basis. The TA model proved to be an effective methodology for evaluating technological issues associated with electric utility planning such as decommissioning nuclear power plants. Through the use of the nominal group technique, the attitudes of a group of residential ratepayers were successfully identified and included in the decision-making process

  15. Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia

    International Nuclear Information System (INIS)

    1969-01-01

    This publication covers nine review papers on the following topics related to the needs and utilization of nuclear reactors in the Boris Kidric Institute of nuclear sciences during previous twenty years: radiochemistry, hot atom chemistry, isotope production, spent nuclear fuel reprocessing, chemistry of transuranium elements; liquid radioactive waste processing, purification of reactor coolant water by inorganic ion exchangers, research related to deuterium concentration processes, and chemical dosimetry at the RA reactor [sr

  16. Current status of operation, utilization and refurbishment of the Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    Pham Duy Hien.

    1993-01-01

    The reconstructed nuclear research reactor at Dalat, Vietnam has been put into operation since March 1984. Up to present a cumulative operation time of 13,172 hrs at nominal power (500 kW) has been recorded. Production of radioisotopes for medical uses, element analysis by using activation techniques, as well as fundamental and applied research with filtered neutrons are the main activities of reactor utilizations. The problems facing Dalat Nuclear Research Institute are the ageing of the re-used TRIGA-MARK-II reactor components (especially the corrosion of the reactor tank), as well as the obsolescence of many equipment and components of the reactor control and instrumentation system. Refurbishment works are being in process with the technical and financial supports from the Vietnam government and the IAEA. (author). 7 refs, 2 tabs, 10 figs

  17. The comparative costs of nuclear and fossil fuelled power plants in an American electricity utility

    International Nuclear Information System (INIS)

    Corey, G.R.

    1984-01-01

    This chapter compares the current and historic operating performances of twelve large nuclear and coal-fired units now operated by Commonwealth Edison Company, and provides specific comparison of bus-bar costs of electricity generated by those units in recent years. It also provides cost comparisons for future nuclear and coal-fired units and attempts to deal realistically with the effect of future inflation upon these comparisons. The chapter attempts to deal responsibly with the problem of uncertainty - how present-day comparisons may be affected by future developments and how my own published comparisons have varied over the past four or five years. The conclusion is reached that, given the uncertain world in which we live, no electric power supplier can afford to put all its eggs in one basket. Utility managers have a strong incentive to diversify their sources of power generation, and society as a whole would do well to encourage such diversification. (author)

  18. Study of the Utilization BWR Type Nuclear Power Reactor for Desalination Process

    International Nuclear Information System (INIS)

    Itjeu Karliana; Sumijanto; Dhandhang Purwadi, M.

    2008-01-01

    The needs of fresh water increased by rapid population growth and industrials expansion, but these demands can not be prepared naturally. Following this case, seawater desalination becomes the primer option which can fulfill the need through the nuclear desalination technology. The coupled nuclear power reactor enables to supply thermal energy for auxiliary equipment and pumps operation. The utilization study of power reactor type BWR coupled with desalination process has been performed. The goal of study is to obtain characteristic data of desalted water specification which desalination system coupling with nuclear power plant produced energy for desalination process. The study is carried out by browsing data and information, and comprehensive review of thermal energy correlation between NPP with desalination process installation. According to reviewing are found that the thermal energy and electric power utilization from the nuclear power reactor are enable to remove the seawater to produce desalted water and also to operate auxiliary equipments. The assessment results is VK-300 reactor prototype, BWR type 250 MW(e) power are cogeneration unit can supplied hot steam temperature 285 °C to the extraction turbine to empower 150 MW electric power, and a part of hot steam 130 °C is use to operate desalination process and remind heat is distribute to the municipal and offices at that region. The coupled of VK-300 reactor power type BWR with desalination installation of MED type enable to produce desalted water with high quality distillate. Based on the economic calculation that the VK-300 reactor power of BWR type produced water distillate capacity is 300.000 m 3 /hour with cost US$ 0.58/m 3 . The coupling VK-300 reactor power type BWR with MED desalination plant is competitive economically. (author)

  19. Multiattribute utility analysis of alternative sites for the disposal of nuclear waste

    International Nuclear Information System (INIS)

    Merkhofer, M.W.; Keeney, R.L.

    1987-01-01

    Five potential sites nominated for the Nation's first geologic repository for disposing of nuclear waste are evaluated using multiattribute utility analysis. The analysis was designed to aid the Department of Energy in its selection of 3 sites for characterization, a detailed data-gathering process that will involve the construction of exploratory shafts for underground testing and that may cost as much as $1 billion per site. The analysis produced insights into the relative advantages and disadvantages of the nominated sites and clarified current uncertainties regarding repository performance

  20. Present status of seawater desalination and problems of nuclear utilization. Aiming at coping with global shortage of water

    International Nuclear Information System (INIS)

    2006-07-01

    With recent global population increase and economic and life level improvement, water demand increases tremendously and in 2025 water scarcity will occur in almost the half of countries and regions in the world. Nuclear desalination is highly expected to cope with this issue. The Japan Atomic Industrial Forum (JAIF) established special committee on seawater desalination problems to discuss possibilities of nuclear desalination introduction. Present status of seawater desalination and problems of nuclear utilization were reviewed and the committee recommended the necessity of establishing medium and long-term plan on international business development of nuclear desalination and also the start of basic research on problems of nuclear utilization such as technical and institutional limits and efficient applicability of nuclear energy. (T. Tanaka)

  1. Development of processes for the utilization of Brazilian coal using nuclear process heat and/or nuclear process steam

    International Nuclear Information System (INIS)

    Bamert, H.; Niessen, H.F.; Walbeck, M.; Wasrzik, U.; Mueller, R.; Schiffers, U.; Strauss, W.

    1980-01-01

    Status of the project: End of the project definition phase and preparation of the planned conceptual phase. Objective of the project: Development of processes for the utilization of nuclear process heat and/or nuclear process steam for the gasification of coal with high ash content, in particular coal from Brazil. Results: With the data of Brazilian coal of high ash content (mine Leao/ 43% ash in the mine-mouth quality, 20% ash after preparation) there have been worked out proposals for the mine planning and for a number of processes. On the basis of these proposals and under consideration of the main data specified by the Brazilian working group there have been choosen two processes and worked out in a conceptual design: 1) pressurized water reactor + LURGI-pressure gasifier/hydrogasification for the production of SNG and 2) high temperature reactor steam gasification for the production of town gas. The economic evaluation showed that the two processes are not substantially different in their cost efficiency and they are economical on a long-term basis. For more specific design work there has been planned the implementation of an experimental programme using the semi-technical plants 'hydrogasification' in Wesseling and 'steam gasification' in Essen as the conceptual phase. (orig.) [de

  2. Research on technology utilizing data freeway for base nuclear power materials

    International Nuclear Information System (INIS)

    Fujita, Mitsutane; Kurihara, Yutaka; Noda, Tetsuji; Shiraishi, Haruki; Kitajima, Masahiro; Nagakawa, Josei; Yamamoto, Norikazu

    1997-01-01

    In order to carry out the selection of the nuclear power materials which are used in radiation, from high temperature to very low temperature, and in corrosive environment, and the development of the materials effectively, the construction of huge material data base is indispensable. The development of the distributed type material data base called 'freeway' is advanced jointly by National Research Institute for Metals, Japan Atomic Energy Research Institute, Power Reactor and Nuclear Fuel Development Corporation and Japan Science and Technology Corporation. It has been aimed at that the results obtained in each research institute are made into a data base by that institute, and those data bases can be utilized mutually through network. In fiscal year 1996, the transfer to the system, by which the function showing the contents of system data and the function of data retrieval can be utilized from internet, was begun jointly. The present state of the data freeway, the operation environment of World Wide Web, and the trial making of the computation program for forecasting the change of the chemical composition of materials by neutron irradiation are reported. (K.I.)

  3. Current status of nuclear research reactor management and utilization program in Thailand

    International Nuclear Information System (INIS)

    Aramrattana, M.; Busamongkol, Y.

    1999-01-01

    The TRR1/M1 is the first research reactor and has been in operational for more than 20 years. During the three decades of research reactor operation in Thailand the utilization of research reactor have been broadened in different fields such as agriculture, medicine and industry. Limitation on utilization of the existing reactor in various fields has led to establishing of a new nuclear research center, Ongkharak Nuclear Research Center (ONRC). The ONRC comprises three major facilities, namely Reactor Island, Isotope Production Facility and Waste Processing and Storage Facility. The reactor itself is a 10 MW TRIGA-type fuels, moderated and cooled by light water with beryllium and heavy water as the reflectors. It is a multi-purpose reactor consisting of different facilities inside and around the core for radioisotope production, medical and industrial uses; and for beam experiments such as High Resolution Powder Diffractometry (HRPD), Neutron Radiography (NR), Prompt Gamma Neutron Activation Analysis (PGNAA), and Boron Neutron Capture Therapy (BNCT). The center is expected to be operational by year 2001. (author)

  4. A Brief Comparative Study on R and D Collaboration Strategy in US and French nuclear utilities

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Sung Tae; Park, Jong Eun [KHNP CRI, Daejeon (Korea, Republic of)

    2014-10-15

    So far KHNP's R and D strategy has been evaluated as 2.5th generation R and D management and R and D investments are focused to the key technologies such as Korea's own nuclear reactor design(like APR1400) development, engineering gap lists elimination(plants trouble shooting), construction/operation process enhancement, etc. But when we compare our R and D strategy with US and France utilities, we can find a lot of differences and the need of improvement to accelerate overseas export of nuclear power plants(technologies) and to be a world top class nuclear operator. One of prominent difference is R and D collaboration strategy. The definition of R and D collaboration has evolved over the years, but for this paper I use it to mean the process where multiple parts of an organization or stake holder work together toward a set of common goals. And by co-funding or cost sharing, collaborative R and D can reduces financial and technical risk and encourages knowledge exchange, supply chain development and in return, collaborative R and D can produce more advanced, complex, effective, efficient R and D products in relatively short time with relatively less budget. UK's technology strategy board estimated that Each we invest in collaborative R and D typically returns around in GVA(Gross Value Added)

  5. Progress in the U.S. nuclear utility industry 1979-1989

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    March 28, 1979 changed the course of the commercial U.S. nuclear utility industry. An accident at Three Mile Island Nuclear Station Unit 2 in Middletown, Pennsylvania damaged the reactor's fuel core, as well as the industry's reputation and confidence. In the months after the event, the president of the United States, the nuclear industry, the public, government regulators and the media sought answers to many questions. Among the most important were, how and why did the accident happen? The President's Commission on the Accident at TMI, the Kemeny Commission, was formed to address these questions. Four major causes were identified by the commission: - inadequate or inappropriate operator training; - mechanical problems and faulty instrumentation; - poor control room design; - communication failures at the facility and in information exchange within the industry. Of even greater importance was another question: How could another such accident be prevented? A look at the industry's progress in the 10 years since the TMI accident shows this question has been vigorously addressed and that corrective actions have been taken.

  6. Development and utilization of the NRC policy statement on the regulation of advanced nuclear power plants

    International Nuclear Information System (INIS)

    Williams, P.M.; King, T.L.

    1988-06-01

    On March 26, 1985, the US Nuclear Regulatory Commission issued for public comment a ''Proposed Policy for Regulation of Advanced Nuclear Power Plants'' (50 FR 11884). This report presents and discusses the Commission's final version of that policy as titled and published on July 8, 1986 ''Regulation of Advanced Nuclear Power Plants, Statement of Policy'' (51 FR 24643). It provides an overview of comments received from the public, of the significant changes from the proposed Policy Statement to the final Policy Statement, and of the Commission's response to six questions contained in the proposed Policy Statement. The report also discusses the definition for advanced reactors, the establishment of an Advanced Reactors Group, the staff review approach and information needs, and the utilization of the Policy Statement in relation to other NRC programs, including the policies for safety goals, severe accidents and standardization. In addition, guidance for advanced reactors with respect to operating experience, technology development, foreign information and data, and prototype testing is provided. Finally, a discussion on the use of less prescriptive and nonprescriptive design criteria for advanced reactors, which the Policy Statement encourages, is presented

  7. On the non-proliferation framework of Japan's peaceful nuclear utilization program

    International Nuclear Information System (INIS)

    Kano, Takashi

    1996-01-01

    The Conference of the States Party to the Treaty on the Non-proliferation of Nuclear Weapons (hereinafter referred to as the NPT) convened in New York, from April 17 to May 12, 1995 and decided that the NPT shall continue in force indefinitely, after reviewing the operation and affirming some aspects of the NPT, while emphasizing the ''Decision on Strengthening the Review Process'' for the NPT and the ''Decision on Principles and Objectives for Nuclear Non-proliferation and Disarmament,'' also adopted by the Conference. In parallel, Japan made its basic non-proliferation policy clear in the ''Long-Term Program for Research, Development and Utilization of Nuclear Energy'' which was decided by the Atomic Energy Commission (chaired by Mikio Oomi, then Minister of the Science and Technology Agency of Japan) in June 1994. The Long-Term Program discusses various problems facing post-Cold-War international society and describes Japan's policy for establishing international confidence concerning non-proliferation. This paper summarizes Japan's non-proliferation policy as articulated in the Long-Term Program, and describes some results of an analysis comparing the Long-Term Program with the resolutions on the international non-proliferation frameworks adopted by the NPT conference

  8. Progress in the U.S. nuclear utility industry 1979-1989

    International Nuclear Information System (INIS)

    1989-01-01

    March 28, 1979 changed the course of the commercial U.S. nuclear utility industry. An accident at Three Mile Island Nuclear Station Unit 2 in Middletown, Pennsylvania damaged the reactor's fuel core, as well as the industry's reputation and confidence. In the months after the event, the president of the United States, the nuclear industry, the public, government regulators and the media sought answers to many questions. Among the most important were, how and why did the accident happen? The President's Commission on the Accident at TMI, the Kemeny Commission, was formed to address these questions. Four major causes were identified by the commission: - inadequate or inappropriate operator training; - mechanical problems and faulty instrumentation; - poor control room design; - communication failures at the facility and in information exchange within the industry. Of even greater importance was another question: How could another such accident be prevented? A look at the industry's progress in the 10 years since the TMI accident shows this question has been vigorously addressed and that corrective actions have been taken

  9. Status of neutron beam utilization at the Dalat nuclear research reactor

    International Nuclear Information System (INIS)

    Dien, Nguyen Nhi; Hai, Nguyen Canh

    2003-01-01

    The 500-kW Dalat nuclear research reactor was reconstructed from the USA-made 250-kW TRIGA Mark II reactor. After completion of renovation and upgrading, the reactor has been operating at its nominal power since 1984. The reactor is used mainly for radioisotope production, neutron activation analysis, neutron beam researches and reactor physics study. In the framework of the reconstruction and renovation project of the 1982-1984 period, the reactor core, the control and instrumentation system, the primary and secondary cooling systems, as well as other associated systems were newly designed and installed by the former Soviet Union. Some structures of the reactor, such as the reactor aluminum tank, the graphite reflector, the thermal column, horizontal beam tubes and the radiation concrete shielding have been remained from the previous TRIGA reactor. As a typical configuration of the TRIGA reactor, there are four neutron beam ports, including three radial and one tangential. Besides, there is a large thermal column. Until now only two-neutron beam ports and the thermal column have been utilized. Effective utilization of horizontal experimental channels is one of the important research objectives at the Dalat reactor. The research program on effective utilization of these experimental channels was conducted from 1984. For this purpose, investigations on physical characteristics of the reactor, neutron spectra and fluxes at these channels, safety conditions in their exploitation, etc. have been carried out. The neutron beams, however, have been used only since 1988. The filtered thermal neutron beams at the tangential channel have been extracted using a single crystal silicon filter and mainly used for prompt gamma neutron activation analysis (PGNAA), neutron radiography (NR) and transmission experiments (TE). The filtered quasi-monoenergetic keV neutron beams using neutron filters at the piercing channel have been used for nuclear data measurements, study on

  10. The diversification value of nuclear power as part of a utility technology mix when gas and carbon prices are uncertain

    International Nuclear Information System (INIS)

    Roques, Fabien A.; Nuttall, William J.; Newbery, David M.; Neufville, Richard de; Connors, Stephen

    2005-01-01

    Despite recent revived interest, the prospects for new nuclear power investment in liberalized electricity industries without government support do not seem promising. The objective of this paper is twofold. First it aims to identify the specific features of nuclear power technology that makes it an unattractive choice. The second objective is to estimate the value to a utility of a nuclear investment as a hedge against uncertain gas and carbon prices. A stylized 5-plant Real Option utility model shows that while the nuclear option value represents about 18% of the net present value (NPV) of the nuclear plant investment in the case where electricity and gas prices are uncorrelated, it reduces to nearly zero for correlation factors between electricity and gas price greater than 30%. These results suggest that the private diversification incentives in electricity markets might not be aligned with the social value of a diverse fuel-mix at the country level. (Author)

  11. Pilot research project of risk communication on nuclear technology and its utilization. Toward communication and collaboration with community

    International Nuclear Information System (INIS)

    Tsuchiya, Tomoko

    2003-01-01

    Although the importance of risk communication has been pointed out over the last decade in nuclear community, both public authorities and nuclear industry have not conducted the definite actions yet. It will be reflected in the public eye that nuclear community's attitude toward communication and consultation with the public about risk issues is half-hearted, comparing with chemical and food safety fields which recently launched their risk communication activities. In this study, we conduct risk communication experiments on some risk issues associated with nuclear technology and its utilization in Tokai village, for the purpose of establishment of risk communication in our society that might be one of the new relationships between science and technology and society. The outcomes of FY2002 study are the following threefold; 1) preparation of risk communication experiments on nuclear technology and its utilization, 2) assessment of social effects of risk communication activities, 3) preparation of practical guidebook for risk communication experiments. (J.P.N.)

  12. Financing the electric power utilities, especially the nuclear power in Japan

    International Nuclear Information System (INIS)

    Tajima, T.

    1975-04-01

    Electric power demands in Japan have shown a remarkable growth at an annual rate of 12% since 1965. Nine electric power companies have invested large amounts of money so far, amounting to over 1 trillion yen every year since 1972. A survey of the electric power supply system and an estimation of the electric power demands in 1980 and in 1985 are given. It is expected that the main portion of electric power in the future will gradually be generated by nuclear plants. Financial features of the electrical power utilities, the credit risk of the electric power utilities, and the raising of funds by electric power utilities are discussed. It is concluded that it will be necessary (1) to expand the capital market, (2) to enable the electric power companies to issue a sufficient amount of bonds, (3) to make the Government financing institutions, such as the Japan Development Bank, provide the electric power companies with larger funds on a long-term and low-interest rate basis, and (4) even to take such drastic steps as subsidizing interest on private loans to the electric power companies. (B.P.)

  13. Advanced Reactor Technology Options for Utilization and Transmutation of Actinides in Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    2009-09-01

    Renewed interest in the potential of nuclear energy to contribute to a sustainable worldwide energy mix is strengthening the IAEA's statutory role in fostering the peaceful uses of nuclear energy, in particular the need for effective exchanges of information and collaborative research and technology development among Member States on advanced nuclear power technologies (Articles III-A.1 and III-A.3). The major challenges facing the long term development of nuclear energy as a part of the world's energy mix are improvement of the economic competitiveness, meeting increasingly stringent safety requirements, adhering to the criteria of sustainable development, and public acceptability. The concern linked to the long life of many of the radioisotopes generated from fission has led to increased R and D efforts to develop a technology aimed at reducing the amount of long lived radioactive waste through transmutation in fission reactors or accelerator driven hybrids. In recent years, in various countries and at an international level, more and more studies have been carried out on advanced and innovative waste management strategies (i.e. actinide separation and elimination). Within the framework of the Project on Technology Advances in Fast Reactors and Accelerator Driven Systems (http://www.iaea.org/inisnkm/nkm/aws/fnss/index.html), the IAEA initiated a number of activities on utilization of plutonium and transmutation of long lived radioactive waste, accelerator driven systems, thorium fuel options, innovative nuclear reactors and fuel cycles, non-conventional nuclear energy systems, and fusion/fission hybrids. These activities are implemented under the guidance and with the support of the IAEA Nuclear Energy Department's Technical Working Group on Fast Reactors (TWG-FR). This publication compiles the analyses and findings of the Coordinated Research Project (CRP) on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste (2002

  14. The effects of SFAS No. 90 and 92 on the stock prices and beta of nuclear electric utilities

    International Nuclear Information System (INIS)

    Romeo, G.C.

    1991-01-01

    In December 1986, the Financial Accounting Standards Board (FASB) issued statement of Financial Accounting Standard (SFAS) Number 90 and in August 1987, issued SFAS No. 92. The new pronouncements differ significantly from the preceding standard, SFAS No. 71, Accounting for the Effects of Certain Types of Regulation. This study investigates whether the market reacts to SFAS No. 90 and 92 events. The sample contained 87 public utilities subdivided into the following portfolios: (1) the Abandonment portfolio, firms that abandoned nuclear plants during 1977 to 1986; (2) the Nuclear-Construction-Delay portfolio, firms that had nuclear construction delays during 1977 to 1986; (3) the Lobbying portfolio, firms that lobbied the FASB; (4) the No-Lobbying portfolio, nuclear firms that did not lobby the FASB; (5) the No Abandonment or Construction-Delay portfolio, nuclear firms that have not abandoned any plants or have not had any construction delays; and (6) the No-Nuclear portfolio, consisting of non-nuclear utility firms. It was found that SFAS No. 90 and 92 produced an effect on the value of firms. Some portfolios of utilities reacted more negatively than the control portfolios. There is also evidence that beta did increase after some events associated with SFAS 90 and 92

  15. Fuzzy logic utilization for the diagnosis of metallic loose part impact in nuclear power plant

    International Nuclear Information System (INIS)

    Oh, Y.-G.; Hong, H.-P.; Han, S.-J.; Chun, C.S.; Kim, B.-K.

    1996-01-01

    In consideration of the fuzzy nature of impact signals detected from the complex mechanical structures in a nuclear power plant under operation. Loose Part Monitoring System with a signal processing technique utilizing fuzzy logic is proposed. In the proposed Fuzzy Loose Part Monitoring System design, comprehensive relations among the impact signal features are taken into account in the fuzzy rule bases for the alarm discrimination and impact event diagnosis. Through the performance test with a mock-up facility, the proposed approach for the loose parts monitoring and diagnosis has been revealed to be effective not only in suppressing the false alarm generation but also in characterizing the metallic loose-part impact event, from the points of Possible Impacted-Area and Degree of Impact Magnitude

  16. Nuclear power and the market value of the shares of electric utilities

    Science.gov (United States)

    Lyons, Joseph T.

    The most basic principle of security valuation is that market prices are determined by investors' expectations of the firm's performance in the future. These expectations are generally understood to be related to the risk that investors will bear by holding the firm's equity. There is considerable evidence that financial statements prepared in accordance with accrual-based accounting standards consistent with Generally Accepted Accounting Principles (GAAP) have information content relevant to the establishment of market prices. In 2001, the Financial Accounting Standards Board (FASB) issued Statement of Financial Accounting Standard No. 143, "Accounting for Asset Retirement Obligations," changing the accounting standards that must be used to prepare financial statements. This paper investigates the effect that investment in nuclear power has on the market value of electric utilities and the impact on the securities markets of the significant changes in financial statement presentation mandated by this new standard.

  17. The Nuclear option for U.S. electrical generating capacity additions utilizing boiling water reactor technology

    International Nuclear Information System (INIS)

    Garrity, T.F.; Wilkins, D.R.

    1993-01-01

    The technology status of the Advanced Boiling Water (ABWR) and Simplified Boiling Water (SBWR) reactors are presented along with an analysis of the economic potential of advanced nuclear power generation systems based on BWR technology to meet the projected domestic electrical generating capacity need through 2005. The forecasted capacity needs are determined for each domestic North American Electric Reliability Council (NERC) region. Extensive data sets detailing each NERC region's specific generation and load characteristics, and capital and fuel cost parameters are utilized in the economic analysis of the optimal generation additions to meet this need by use of an expansion planning model. In addition to a reference case, several sensitivity cases are performed with regard to capital costs and fuel price escalation

  18. The BRO proteins of Bombyx mori nucleopolyhedrovirus are nucleocytoplasmic shuttling proteins that utilize the CRM1-mediated nuclear export pathway

    International Nuclear Information System (INIS)

    Kang, Won Kyung; Kurihara, Masaaki; Matsumoto, Shogo

    2006-01-01

    The BRO proteins of Bombyx mori nucleopolyhedrovirus (BmNPV) display a biphasic pattern of intracellular localization during infection. At early times, they reside in the nucleus but then show both cytoplasmic and nuclear localization as the infection proceeds. Therefore, we examined the possibility of nuclear export. Using inhibitors, we reveal that BmNPV BRO proteins shuttle between the nucleus and cytoplasm. Mutations on the leucine-rich region of BRO proteins resulted in nuclear accumulation of transiently expressed proteins, suggesting that this region functions as a CRM1-dependent nuclear export signal (NES). On the contrary, mutant BRO-D with an altered NES did not show nuclear accumulation in infected cells, although protein production seemed to be reduced. RT-PCR analysis showed that the lower level of protein production was due to a reduction in RNA synthesis. Taken together, our results suggest that BRO proteins are nucleocytoplasmic shuttling proteins that utilize the CRM1-mediated nuclear export pathway

  19. Burnup verification measurements at a US nuclear utility using the FORK measurement system

    International Nuclear Information System (INIS)

    Ewing, R.I.; Bosler, G.E.; Walden, G.

    1993-01-01

    The FORK measurement system, designed at Los Alamos National Laboratory (LANL) for the International Atomic Energy Agency (IAEA) safeguards program, has been used to examine spent reactor fuel assemblies at Duke Power Company's Oconee Nuclear Station. The FORK system measures the passive neutron and gamma-ray emission from spent fuel assemblies while in the storage pool. These measurements can be correlated with burnup and cooling time, and can be used to verify the reactor site records. Verification measurements may be used to help ensure nuclear criticality safety when burnup credit is applied to spent fuel transport and storage systems. By taking into account the reduced reactivity of spent fuel due to its burnup in the reactor, burnup credit results in more efficient and economic transport and storage. The objectives of these tests are to demonstrate the applicability of the FORK system to verify reactor records and to develop optimal procedures compatible with utility operations. The test program is a cooperative effort supported by Sandia National Laboratories, the Electric Power Research Institute (EPRI), Los Alamos National Laboratory, and the Duke Power Company

  20. Evaluation of utility monitoring and preoperational hydrothermal modeling at three nuclear power plant sites

    International Nuclear Information System (INIS)

    Marmer, G.J.; Policastro, A.J.

    1977-01-01

    This paper evaluates the preoperational hydrothermal modeling and operational monitoring carried out by utilities as three nuclear-power-plant sites using once-through cooling. Our work was part of a larger study to assess the environmental impact of operating plants for the Nuclear Regulatory Commission (NRC) and the suitability of the NRC Environmental Technical Specifications (Tech Specs) as set up for these plants. The study revealed that the plume mappings at the Kewaunee, Zion, and Quad Cities sites were generally satisfactory in terms of delineating plume size and other characteristics. Unfortunately, monitoring was not carried out during the most critical periods when largest plume size would be expected. At Kewaunee and Zion, preoperational predictions using analytical models were found to be rather poor. At Kewaunee (surface discharge), the Pritchard Model underestimated plume size in the near field, but grossly overestimated the plume's far-field extent. Moreover, lake-level variations affected plume dispersion, yet were not considered in preoperational predictions. At Zion (submerged discharge) the Pritchard Model was successful only in special, simple cases (single-unit operation, no stratification, no reversing currents, no recirculation). Due to neglect of the above-mentioned phenomena, the model underpredicted plume size. At Quad Cities (submerged discharge), the undistorted laboratory model predicted plume dispersion for low river flows. These low flow predictions appear to be reasonable extrapolations of the field data acquired at higher flows

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

    Science.gov (United States)

    Venetoklis, Peter S.

    1995-01-01

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

  2. Analysis of good governance towards optimizing of nuclear energy utilization in Indonesia

    International Nuclear Information System (INIS)

    Eko Riyadi

    2011-01-01

    Good Governance is very influential in the process of government organization, especially related to information technology (IT Governance), that its implementation will ensure organizational transparency, efficiency and effectiveness. It can even avoid the formation of islands-of-information that not only making ineffective governance, but also potentially cause data integrity problems at later. To support the optimization of monitoring the nuclear energy utilization in Indonesia, Nuclear Energy Regulatory Agency (BAPETEN) should implement this IT Governance, which can be applied when an organization already know the IT maturity level in support of his organization. Assessment of IT maturity level can be conducted using a best practice such as Control Objectives for Information and Related Technology (CobiT), which has been recognized internationally. Then determine a target of IT maturity that want to be achieved, by determining the Critical Success Factor (CSF) including recommendations for its achievement. In addition, the determination of the impact and effort needs to be conducted to get the prioritization of the CSF achievement. The next step is establishing Key Performance Indicator (KPI) that can measure the success rate of performance, so that organizational goals to provide excellent service to the community can be realized easily. (author)

  3. UMCP-BG and E collaboration in nuclear power engineering in the framework of DOE-Utility Nuclear Power Engineering Education Matching Grant Program

    Energy Technology Data Exchange (ETDEWEB)

    Wolfe, Lothar PhD

    2000-03-01

    The DOE-Utility Nuclear Power Engineering Education Matching Grant Program has been established to support the education of students in Nuclear Engineering Programs to maintain a knowledgeable workforce in the United States in order to keep nuclear power as a viable component in a mix of energy sources for the country. The involvement of the utility industry ensures that this grant program satisfies the needs and requirements of local nuclear energy producers and at the same time establishes a strong linkage between education and day-to-day nuclear power generation. As of 1997, seventeen pairs of university-utility partners existed. UMCP was never a member of that group of universities, but applied for the first time with a proposal to Baltimore Gas and Electric Company in January 1999 [1]. This proposal was generously granted by BG&E [2,3] in the form of a gift in the amount of $25,000 from BG&E's Corporate Contribution Program. Upon the arrival of a newly appointed Director of Administration in the Department of Materials and Nuclear Engineering, the BG&E check was deposited into the University's Maryland Foundation Fund. The receipt of the letter and the check enabled UMCP to apply for DOE's matching funds in the same amount by a proposal.

  4. Energy Research Advisory Board, Civilian Nuclear Power Panel: Subpanel 1 report, Light water reactor utilization and improvement: Volume 2

    International Nuclear Information System (INIS)

    1986-10-01

    The Secretary of Energy requested that the Office of Nuclear Energy prepare a strategic national plan that outlines the Department's role in the future development of civilian nuclear power and that the Energy Research Advisory Board establish an ad hoc panel to review and comment on this plan. The Energy Research Advisory Board formed a panel for this review and three subpanels were formed. One subpanel was formed to address the institutional issues surrounding nuclear power, one on research and development for advanced nuclear power plants and a third subpanel on light water reactor utilization and improvement. The subpanel on light water reactors held two meetings at which representatives of the DOE, the NRC, EPRI, industry and academic groups made presentations. This is the report of the subpanel on light water reactor utilization and improvement. This report presents the subpanel's assessment of initiatives which the Department of Energy should undertake in the national interest, to develop and support light water reactor technologies

  5. Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

    Directory of Open Access Journals (Sweden)

    Seung Hyun Nam

    2015-10-01

    Full Text Available Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER, for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MWth and an electricity generation mode of 100 kWth, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and

  6. Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Seung Hyun; Venneri, Paolo; Kim, Yong Hee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2015-10-15

    Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MW{sub th} and an electricity generation mode of 100 kW{sub th}, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and

  7. Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

    International Nuclear Information System (INIS)

    Nam, Seung Hyun; Venneri, Paolo; Kim, Yong Hee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon

    2015-01-01

    Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MW th and an electricity generation mode of 100 kW th , equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and thermohydraulics

  8. Utilization of Used Nuclear Fuel in a Potential Future US Fuel Cycle Scenario - 13499

    Energy Technology Data Exchange (ETDEWEB)

    Worrall, Andrew [Oak Ridge National Laboratory, P.O. BOX 2008 MS6172, Oak Ridge, TN, 37831-6172 (United States)

    2013-07-01

    from the FRs due to time in the core, cooling time, reprocessing, and re-fabrication time is built into the analysis, along with impacts in delays and other key assumptions and sensitivities have been investigated. The results of this assessment highlight how the UNF from future reactors (LWRs and FRs) and the resulting fissile materials (U and Pu) from reprocessing can be effectively utilized, and show that the timings of future nuclear programs are key considerations (both for reactors and fuel cycle facilities). The analysis also highlights how the timings are relevant to managing the UNF and how such an analysis can therefore assist in informing the potential future R and D strategy and needs of the US fuel cycle programs and reactor technology. (authors)

  9. Utilization of Used Nuclear Fuel in a Potential Future US Fuel Cycle Scenario - 13499

    International Nuclear Information System (INIS)

    Worrall, Andrew

    2013-01-01

    from the FRs due to time in the core, cooling time, reprocessing, and re-fabrication time is built into the analysis, along with impacts in delays and other key assumptions and sensitivities have been investigated. The results of this assessment highlight how the UNF from future reactors (LWRs and FRs) and the resulting fissile materials (U and Pu) from reprocessing can be effectively utilized, and show that the timings of future nuclear programs are key considerations (both for reactors and fuel cycle facilities). The analysis also highlights how the timings are relevant to managing the UNF and how such an analysis can therefore assist in informing the potential future R and D strategy and needs of the US fuel cycle programs and reactor technology. (authors)

  10. The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario

    International Nuclear Information System (INIS)

    King, Wayne E.; Bradley, Keith; Jones, Edwin D.; Kramer, Kevin J.; Latkowski, Jeffery F.; Robel, Martin; Sleaford, Brad W.

    2010-01-01

    Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a 'figure of merit' (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit into an assessment of a nuclear material theft scenario and its use in the assessment. This paper demonstrates that material attractiveness is a multidimensional concept that embodies more than the FOM. It also seeks to propose that other attributes may be able to be quantified through analogous FOMs (e.g., transformation) and that, with quantification, aggregation may be possible using concepts from the risk community.

  11. The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario

    Energy Technology Data Exchange (ETDEWEB)

    King, Wayne E., E-mail: weking@llnl.go [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Bradley, Keith [Global Security Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Jones, Edwin D. [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Kramer, Kevin J.; Latkowski, Jeffery F. [Engineering Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Robel, Martin [Physical and Life Sciences Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States); Sleaford, Brad W. [Engineering Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)

    2010-11-15

    Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a 'figure of merit' (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit into an assessment of a nuclear material theft scenario and its use in the assessment. This paper demonstrates that material attractiveness is a multidimensional concept that embodies more than the FOM. It also seeks to propose that other attributes may be able to be quantified through analogous FOMs (e.g., transformation) and that, with quantification, aggregation may be possible using concepts from the risk community.

  12. Views of the electric utility industry on the direction and progress of the Department of Energy's Nuclear Waste Program

    International Nuclear Information System (INIS)

    Mills, L.E.

    1986-01-01

    The NWPA does provide guidance for a reasonable waste management program and one must work to implement it in an efficient and effective manner. It is well recognized that the lack of stability and predictability has been the bane of many nuclear reactor projects. The electric utilities are not satisfied with the progress of the nuclear waste program even though much has been achieved. DOE must continue in its struggle to seek a better balance between the technical, political and institutional aspects of the program to provide reasonable assurance that it will fulfill its contractual obligation with utilities

  13. Advanced orient cycle, for strategic separation, transmutation and utilization of nuclides in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Ozawa, M.; Fujita, R.; Koyama, S.; Suzuki, T.; Fujii, Y.

    2007-01-01

    Electrolytic extraction (EE) method has been studied as a vital separation tool for new reprocessing process to realize transmutation and utilization of the specific fission products including LLFP * (e.g., Tc * , Ru, Rh, Pd * , Se * and Te * , etc) in the spent nuclear fuel. In an employed EE process, Pd 2 + cation itself would not only be easily (>99%) deposited from various nitric acid solutions, but enhance also the deposition of co-existing RuNO 3 + and ReO 4 - by acting as a catalyst (as Pd a datom). Such a catalytic electrolytic extraction (i.e., CEE) method was also applicable in the case of 9 9TcO 4 - deposition as well. Addition of Pd 2 + caused either to change the dendritic metal deposition form or to improve electrochemical property of deposits. The RMFP deposit, especially quaternary-, Pd-Ru-Rh-Re, deposits on the Pt electrode obtained by the CEE method were rather spherical in shape, seemed to be electrochemically agglomerated by nano particles. The deposits were stable and showed electrochemically nobler initial hydrogen evolution potential (φ H int.). Also in the given potential of -1.25 V (vs. Ag/AgCl), the quaternary-, Pd-Ru-Rh-Re, deposit Pt electrode suggested the highest cathodic current corresponding to the hydrogen generation reaction. Namely, those catalytic activities were ca. twice superior to that of the Pt electrode in alkaline solution. The sea water is a possible resource for hydrogen production in future. In the course of sea water electrolysis, disturbance due to Ca(OH) 2 and Mg(OH) 2 precipitation was inevitable, but the cathodic current of the quaternary deposit of RMFP was the highest, the same as to that of Pt electrode in the alkaline water. Therefore, RMFP has a potential to alternate with Pt catalyst. The electrochemical property of Re and 9 9Tc, as for alternative element to Re, are under investigation with a special interest of this direction of utilization. The renovative reprocessing flow sheet by tertiary pyridine resin

  14. Cost structure analysis of commercial nuclear power plants in Japan based on corporate financial statements of electric utility companies

    International Nuclear Information System (INIS)

    Kunitake, Norifumi; Nagano, Koji; Suzuki, Tatsujiro

    1998-01-01

    In this paper, we analyze past and current cost structure of commercial nuclear power plants in Japan based on annual corporate financial statements published by the Japanese electric utility companies, instead of employing the conventional methodology of evaluating the generation cost for a newly constructed model plant. The result of our study on existing commercial nuclear plants reveals the increasing significance of O and M and fuel cycle costs in total generation cost. Thus, it is suggested that electric power companies should take more efforts to reduce these costs in order to maintain the competitiveness of nuclear power in Japan. (author)

  15. Study on public awareness of utilizing nuclear power in China. Changes in public awareness after the accident of Fukushima Daiichi Nuclear Power Plants

    International Nuclear Information System (INIS)

    Xu, Ting; Wakabayashi, Toshio

    2012-01-01

    The purpose of this study is to clarify public awareness of utilizing nuclear power in China and to determine the effects of the accident of Fukushima Daiichi nuclear power plants. Web online surveys were carried out before and after the accident of Fukushima Daiichi nuclear power plants. The online survey before the accident of Fukushima Daiichi nuclear power plants had 4,255 adult respondents consisting of 1,851 males and 2,404 females. The online survey after the accident had 721 respondents consisting of 406 males and 315 females. The two online surveys about the attitude toward nuclear power plants consisted of 37 items, such as the necessity of nuclear power plants, the reliability of safety, and government confidence. As a result, respondents of the online surveys in China consider that nuclear energy is more important than the anxiety of accident. On the other hand, women have sensation of fear for the accident of Fukushima Daiichi nuclear power plants and radiation. (author)

  16. Overlapping Nuclear Safety Control Provisions of the Atomic Energy Act and Electric Utility Act

    International Nuclear Information System (INIS)

    Chang, Gun-Hyun; Kim, Sang-Won; Koh, Jae-Dong; Ahn, Hyung-Joon; Kim, Chang-Bum

    2007-01-01

    Before May 17, 2005, Korea's nuclear power plant (hereinafter referred to as 'NNP') regulation system was two-pronged. Every NPP system consists of primary or secondary system, and each type was respectively regulated by the Atomic Energy Act(hereinafter referred to as 'AEA') and the Electric Utility Act(hereinafter referred to as 'EUA'). This unusual regulatory regime gave rise to a number of problems with respect to operation and safety. For this reason, the Enforcement Regulation of AEA and applicable Notice were revised on May 17, 2005 to the effect that all regulation on NPPs subject to EUA was brought under the purview of AEA, except regulation on business license for nuclear power generation under Article 7 of EUA and approval of plan of works for setting up electric installations (hereinafter referred to as 'construction plan') (including approval of any changes; the same shall apply hereinafter) under Article 61 thereof. From the point of view of the Ministry of Science and Technology, the regulation of NPPs by a single law has enhanced their safety. However, the Ministry of Commerce, Industry and Energy retains regulatory authority regarding NPPs. It reviews and approves construction plans for secondary system pursuant to Article 61 of EUA and Article 28 of the Enforcement Regulation thereof. This situation arose because Article 28 of the Enforcement Regulation of EUA continues to provide for matters related with nuclear power. Therefore, continued control of NPPs under EUA ignores the relationship and respective nature of AEA and EUA. There is also possibility of violation of a superseding law. Even if said provision is not in violation of a superseding law, Article 28 of the Enforcement Regulation of EUA poses the possibility of overlapping regulation, which may violate the principle of prohibiting excessive regulation, one of the principles of the Korean Constitution. Assessment of the dual regulatory system for review of secondary system requires (i

  17. Direct utilization of information from nuclear data files in Monte Carlo simulation of neutron and photon transport

    International Nuclear Information System (INIS)

    Androseno, P.; Zholudov, D.; Kompaniyets, A.; Smirnova, O.

    2000-01-01

    In order to improve both the economics of Nuclear Power Plants (NPPs) as well as their safety, data and computer codes that perform benchmark calculations while simulating NPP parameters must be utilized. This work is mainly concerned with application of computer codes using the Monte Carlo method, which provides advanced accuracy of equations to be calculated. (authors)

  18. Utility of multispectral imaging for nuclear classification of routine clinical histopathology imagery

    Directory of Open Access Journals (Sweden)

    Harvey Neal R

    2007-07-01

    Full Text Available Abstract Background We present an analysis of the utility of multispectral versus standard RGB imagery for routine H&E stained histopathology images, in particular for pixel-level classification of nuclei. Our multispectral imagery has 29 spectral bands, spaced 10 nm within the visual range of 420–700 nm. It has been hypothesized that the additional spectral bands contain further information useful for classification as compared to the 3 standard bands of RGB imagery. We present analyses of our data designed to test this hypothesis. Results For classification using all available image bands, we find the best performance (equal tradeoff between detection rate and false alarm rate is obtained from either the multispectral or our "ccd" RGB imagery, with an overall increase in performance of 0.79% compared to the next best performing image type. For classification using single image bands, the single best multispectral band (in the red portion of the spectrum gave a performance increase of 0.57%, compared to performance of the single best RGB band (red. Additionally, red bands had the highest coefficients/preference in our classifiers. Principal components analysis of the multispectral imagery indicates only two significant image bands, which is not surprising given the presence of two stains. Conclusion Our results indicate that multispectral imagery for routine H&E stained histopathology provides minimal additional spectral information for a pixel-level nuclear classification task than would standard RGB imagery.

  19. Issues to be resolved for the successful implementation of the Nuclear Waste Policy Act of 1982: Utilities' viewpoint

    International Nuclear Information System (INIS)

    Kauffman, J.T.; Kraft, S.P.

    1987-01-01

    This article describes issues that utility companies perceive as important for successful implementation of the NWPA. Electric utility companies with nuclear energy programs are fulfilling their commitments under the NWPA by paying over $400 million a year into the Nuclear Waste Fund as well as preparing for on-site storage of spent fuel until 1998. The current impasse in Congress over DOE's recommend second repository reprogramming is giving the industry pause to consider whether or not DOE will be allowed by Congress to live up to its 1998 obligation to the utilities. The industry is asking Congress to allow DOE to proceed with characterization of the three potential first sites, to authorize and fund the MRS, and to provide equitable payments for defense waste disposal. Also, Congress and DOE must work cooperatively to find a solution to the current impasse over the second repository program

  20. Substantial Variability Exists in Utilities' Nuclear Decommissioning Funding Adequacy: Baseline Trends (1997-2001); and Scenario and Sensitivity Analyses (Year 2001)

    International Nuclear Information System (INIS)

    Williams, D. G.

    2003-01-01

    This paper explores the trends over 1997-2001 in my baseline simulation analysis of the sufficiency of electric utilities' funds to eventually decommission the nation's nuclear power plants. Further, for 2001, I describe the utilities' funding adequacy results obtained using scenario and sensitivity analyses, respectively. In this paper, I focus more on the wide variability observed in these adequacy measures among utilities than on the results for the ''average'' utility in the nuclear industry. Only individual utilities, not average utilities -- often used by the nuclear industry to represent its funding adequacy -- will decommission their nuclear plants. Industry-wide results tend to mask the varied results for individual utilities. This paper shows that over 1997-2001, the variability of my baseline decommissioning funding adequacy measures (in percentages) for both utility fund balances and current contributions has remained very large, reflected in the sizable ranges and frequency distributions of these percentages. The relevance of this variability for nuclear decommissioning funding adequacy is, of course, focused more on those utilities that show below ideal balances and contribution levels. Looking backward, 42 of 67 utility fund (available) balances, in 2001, were above (and 25 below) their ideal baseline levels; in 1997, 42 of 76 were above (and 34 below) ideal levels. Of these, many utility balances were far above, and many far below, such ideal levels. The problem of certain utilities continuing to show balances much below ideal persists even with increases in the adequacy of ''average'' utility balances

  1. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

  2. Utilization of nuclear energy for generating electric power in the FRG, with special regard to LWR-type reactors

    International Nuclear Information System (INIS)

    Vollradt, J.

    1977-01-01

    Comments on interdependencies in energy industry and energy generation as seen by energy supply utilities, stating that the generation of electric power in Germany can only be based on coal and nuclear energy in the long run, are followed by the most important, fundamental, nuclear-physical, technological and in part political interdependencies prevailing in the starting situation of 1955/58 when the construction of nuclear power plant reactors began. Then the development ranging to the 28000 MW nuclear power output to be expected in 1985 is outlined, totalling in 115000 MW electric power in the FRG. Finally, using the respectively latest order, the technical set up of each of the reactor types with 1300 MWe unit power offered by German manufacturers are described: BBC/BBR PWR-type reactor Neupotz, KWU-PWR-type reactor Hamm and KWU PWR-type reactor double unit B+C Gundremmingen. (orig.) [de

  3. Risks in production and utilisation of labelled compounds for nuclear medicine. 2. Benefits and risks of utilization of 99mTc generator in nuclear medicine

    International Nuclear Information System (INIS)

    Olteanu-Chiper, D.; Barna, C.; Gard, E.; Negoita, N.

    1999-01-01

    The growth of radioisotope applications in nuclear medicine, imposed the reduction of the radiation effects and so, the reduction of associated risk of these applications. The utilization of radioactive isotopes for investigations in nuclear medicine is conditioned by the chemical behaviour and the means of detection of the emitted radiation on one hand, and by the radiation doses received by the patient, on the other hand. In these conditions, the nuclear medicine uses only the radioisotopes which are short half-time and low radiation energy, but high enough to be detected from the exterior of human body, 99m Tc being the most favourable for utilization in diagnostic purpose. This advantage is increased by the multiple possibilities to obtain different chemical forms with 99m Tc included, which permit the production of a large variety of radiopharmaceutical products, having a specific localization in the human body (organ-targets), thus allowing the diagnosis of numerous diseases. In the work the benefits and risks of the 99m Tc-Generator utilization in the nuclear medicine are shown and the utilization technique in these applications is presented . The 99m Tc-Generator is a compact chromatographic system, with lead shielding, which permits the elution of a sterile, pyrogen-free, injectable sodium pertechnetate solution, from an aluminium chromatographic column which keeps the 99 Mo. The 99m Tc-Generator system ensures the operator protection. The radioactive solution with 99m Tc is obtained in a closed vial, within lead shielding, the irradiation or contamination risks being mostly reduced. The utilization of 99m Tc in scintigraphic exam for diagnostic medicine implies a labelling operation with 99m Tc chemically bounded in forms appropriate to the target-organ and than the intravenously injection in doses dependent on the specific scintigraphic investigation or examination. (authors)

  4. Guidelines and workbook for assessment of organization and administration of utilities seeking operating license for a nuclear power plant. Guidelines for utility organization and administration plan. Volume 1

    International Nuclear Information System (INIS)

    Thurber, J.A.; Olson, J.; Osborn, R.N.; Sommers, P.; Widrig, R.D.

    1985-08-01

    The Guidelines are intended to provide guidance to the user in preparing a written plan for a proposed nuclear organization and administration. The Guidelines allow for individual approaches to organizational structures to account for differences in plant size, number of operating units, number of plant sites, and the individual utility approach to providing technical support. These unique approaches, however, should meet the criteria of a reasoned, fully developed, and logically consistent focus on the user's organization in terms of organization of work, policies and procedures, staffing, and external relationships

  5. A study on the enhancement of nuclear cooperation with African countries including utilization of radioisotope

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Maeng Ho; Oh, K. B; Lee, H. M. and others

    2005-05-15

    In this study, potential countries for nuclear cooperation in African region and possible cooperation areas were investigated between Korea and African countries including radioisotopes and more fields were also analysed in depth in order to suggest the recommendations for future cooperation to be considered as follows; First, current status and perspectives of demand and supply of energy and electricity in the African countries, use and development of nuclear energy and international nuclear cooperation were analyzed. Second, current status of nuclear cooperation between Korea and African countries were investigated as well as analysis of future cooperation potential and countries having potential for nuclear cooperation and possible cooperative activities were suggested considering potential of nuclear market in mid- and long term base and step by step. Third, desirable strategies and directions for the establishment and promotion of nuclear cooperation relations between Korea and African developing countries were suggested in order to develope cooperative relations in efficient and effective manners with African developing countries.

  6. A study on the enhancement of nuclear cooperation with African countries including utilization of radioisotope

    International Nuclear Information System (INIS)

    Yang, Maeng Ho; Oh, K. B; Lee, H. M. and others

    2005-05-01

    In this study, potential countries for nuclear cooperation in African region and possible cooperation areas were investigated between Korea and African countries including radioisotopes and more fields were also analysed in depth in order to suggest the recommendations for future cooperation to be considered as follows; First, current status and perspectives of demand and supply of energy and electricity in the African countries, use and development of nuclear energy and international nuclear cooperation were analyzed. Second, current status of nuclear cooperation between Korea and African countries were investigated as well as analysis of future cooperation potential and countries having potential for nuclear cooperation and possible cooperative activities were suggested considering potential of nuclear market in mid- and long term base and step by step. Third, desirable strategies and directions for the establishment and promotion of nuclear cooperation relations between Korea and African developing countries were suggested in order to develope cooperative relations in efficient and effective manners with African developing countries

  7. Status and development of nuclear energy utilization in the Federal Republic of Germany - December 1992

    International Nuclear Information System (INIS)

    Philippczyk, F.; Ziegenhagen, J.

    1993-05-01

    The report states the essential data of all nuclear power plants, the nuclear fuel cycle facilities and the storage of radioactive wastes. In 1992, 20 nuclear power plants were in operation. With 158.840 GWh altogether they provided 32% of the total gross electricity production. The report summarizes the essential operational results of the nuclear power plants as well as the use of mixed oxide fuel elements (MOX). A short description of the present state of the nuclear power plants that have been shut down or decommissioned and of the stopped programmes is given. Data on purpose and capacity of facilities of the nuclear fuel cycle and of radioactive waste storage are given. Furthermore, the licensing history and the present state of operation and licensing are represented. Three projects with regard to disposal of radioactive wastes are presented according to their present state. (orig.) [de

  8. Effects of degree of approval and message on utility of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Tanigaki, Toshihiko

    2007-01-01

    It is said that the effectiveness of nuclear power generation is the greatest factor contributing to whether or not people support the nuclear power policy. The major objectives of this research are twofold: from among opinions regarding the effectiveness of the nuclear fuel cycle, to clarify what kinds of opinions people support and what kinds of opinions have influenced judgments about the pros and cons of the nuclear fuel cycle; and to measure the extent to which people's awareness of the nuclear fuel cycle is influenced by numerical information that has been added to a nuclear-fuel-cycle-related message that has been created on the basis of results of the survey conducted for the first objective mentioned above. As for the first objective, the survey results revealed that the opinion 'the establishment of a nuclear fuel cycle leads to the effective use of energy resources' did not garner much support from the public. However, it was indicated that people being for or against that opinion may have relatively great effect on their judgment regarding the pros and ons of nuclear fuel cycle establishment. For the second objective, we showed people the messages the nuclear fuel cycle enables effective use of natural uranium' and 'the nuclear fuel cycle enables tens times more effective use of natural uranium' to the latter of which numerical information was added. As a result, we found no difference in people's attitude toward the nuclear fuel cycle even if numerical information was added to a nuclear-fuel-cycle-related message. (author)

  9. Nuclear liability insurance problems and trends as seen by the European utilities

    International Nuclear Information System (INIS)

    Gulck, Albert van.

    1978-01-01

    After recalling the basic principles of nuclear civil liability conventions, the author describes the different types of damage presently covered by nuclear insurance. Also, a Study Committee was created in Western Europe in 1974 to examine the possibility of setting up a mutual pool to cover risks such as fire and property damage in nuclear installations. In the immediate future machinery breakdown and all risk coverage on-site will not be covered. This mutual pool will widen the nuclear insurance market in the coming decades. (NEA) [fr

  10. Nuclear option: one of several choices open to electric utilities; the European case

    International Nuclear Information System (INIS)

    Charrault, J.C.

    1983-01-01

    Acknowledging a difference of opinion on nuclear energy between the US and Europe, the author states the European Community's main energy problems and the solutions that are planned, gives the economic aspects of interfuel competition for electricity generation, and promotes nuclear energy as a secure source of electricity supply. Fast-breeder-reactor (FBR) technology and nuclear-fusion technology are discussed as the reliable successors to nuclear power in the beginning of the next century when uranium shortages and failing renewable energy substitutes will be inadequate to meet Europe's electricity needs

  11. Data gathering in support of phase O program for waste heat utilization from nuclear enrichment facilities, Ohio

    International Nuclear Information System (INIS)

    1978-01-01

    The gathering of demographic, community development, and economic data for the region impacted by the Pikeville (Ohio) Nuclear Enrichment Facility is described. These data are to be used for establishing possible community uses, e.g., space heating, domestic water heating, and industrial uses, of waste heat from the facility. It was concluded that although the economic feasibility of such waste heat utilization remains to be proven, the community would cooperate in a feasibility demonstration program

  12. Experimental study of the combined utilization of nuclear power heating plants for big towns and industrial complexes

    International Nuclear Information System (INIS)

    Neumann, J.; Barabas, K.

    1977-01-01

    The paper describes a comparison of nuclear power heating plants with an output corresponding to 1000MW(e) with plants of the same output using coal or oil. The economic aspects are compared, both as regards investment and operation costs. The comparison of the environmental aspects is performed on the atmospheric pollution from exhausts and gaseous emission and on the thermal pollutions in hydrosphere and atmosphere. Basic nuclear power plant schemes with two PWRs, each of 1500MW(th), are described. The plant supplies electric power and heat for factories and municipal heating systems (apartments, shops, and other auxiliary municipal facilities). At the same time the basic heat-flow diagram of a nuclear power heating plant is given, together with the relative losses. The study emphasizes the possible utilization of waste heat for heating glasshouses of 200m 2 . The problems of utilizing waste heat, and the needs of a big town and of industrial complexes in the vicinity of the nuclear power heating plant are also considered. (author)

  13. State and development of nuclear energy utilization in the Federal Republic of Germany 2012

    Energy Technology Data Exchange (ETDEWEB)

    Bredberg, Ines; Hutter, Johann; Kuehn, Kerstin; Philippczyk, Frank; Dose, Julia

    2013-11-15

    This report describes the use of nuclear energy in the Federal Republic of Germany as of December 2012. It contains the essential data of all nuclear power plants, research reactors and the facilities of the nuclear fuel cycle. At the reporting moment 31{sup st} of December in 2012, nine nuclear power plants were still in operation. The power generation from nuclear energy in 2012 amounted to 99.5 TWh (2011: 108.0 TWh). That is a share of 16.1 % of the total gross electricity production (2011: 17.7 %). The report summarises the essential operational results of the nuclear power plants and information on granted licences. A short description of the present state of the nuclear power plants that have been shut down or decommissioned and of the stopped projects is given. Concerning research reactors essential data on type, characteristics (thermal power, thermal neutron flux) and purpose of the facility are represented. Furthermore, an overview of the licensing and operation history and the present state of the operating condition is given. For the facilities of the nuclear fuel cycle data on purpose and capacity, the licensing history and the present state of operation and licensing are given. The current status of repository projects is presented. To give a survey, the data is summarised in tabular form in the report Annexes. The report will be updated and published once a year.

  14. Considerations about the utilization of electrically heated rods used for simulation of nuclear fuel pins

    International Nuclear Information System (INIS)

    Lima, R. de C.F. de; Carajilescov, P.

    1987-01-01

    The dinamic behavior of electrically heated rods used for simulation of nuclear fuel pins in nuclear power transients, is analysed by the application of the lumped parameter and the finite difference methods. Deviations of the rods surface conditions, for extreme accidental transient conditions are presented and discussed. (author) [pt

  15. The safe and peaceful utilization of nuclear energy in the dynamic Pacific basin

    International Nuclear Information System (INIS)

    Blix, H.

    1994-01-01

    In the Pacific region, as elsewhere, nuclear techniques have an established role in industry, medicine, and agricultural science. There is also a growing appreciation for the usefulness of nuclear techniques in tackling environmental problems. The risk of misuse and unsafe use remains the major issue

  16. EDF, a utility and its own needs in the field of transport of nuclear materials

    International Nuclear Information System (INIS)

    Gouin, P.; Mignot, E.; Hoang, L.P.

    1989-01-01

    As one of the most important producers of nuclear electricity in the world, EDF is concerned by all the aspects of the transport of nuclear materials and more particularly by those related to the nuclear fuel cycle. EDF is not itself a specialist in this field and most of the transports along the nuclear fuel cycle is done for their own account by their usual partners such as COGEMA or TRANSNUCLEAIRE. Since the beginning of the French nuclear program, they have generally used for these transports casks that already exist on the market and which were well suited to their needs. Nevertheless, new and specific needs appeared during the progress of their nuclear program and have lead them to: study and build new casks or packages, use existing casks for new purposes, develop a device for the measurement of fuel assemblies burn up, develop a software to optimize the evacuation of irradiated fuel for reprocessing. The purpose of this paper is to describe these realization but as a preliminary, they will present briefly the importance of the transport of nuclear materials for EDF

  17. A study on enhancing the utilization of nuclear power in Korea

    International Nuclear Information System (INIS)

    Choi, Young Myung; Han, Do Hee; Lee, Byung Wook; Lee, Kwang Seok; Lee, Jae Sung; Choi, Young Lok; Jo, Se Hyun; Lee, Han Myung; Won, Byung Chool; Park, Sung Gi

    1992-01-01

    As the world recognizes the global warming problem as an important issue it has to solve, nuclear power is being considered as a way to solve the problem. This study reviews (1) what the global warming problem is, (2) why the problem occurs, and (3) how the problem can be solved. This study also review international effort to solve the problem in terms of intergovernmental negotiation on climate change and its effect on Korea. This study discusses the role of nuclear power in solving the problem, contrasting the argument of those who object to the use of nuclear power. With the argument of those who agree to the use of nuclear power. This study reviews and analyzes recent changes in the international nuclear society; especially fortification of special inspection and safeguards by the IAEA, and attempt to append dual purpose items to London Guidelines. This study reviews the history of the Nuclear Non-Proliferation Act in the USA in terms of its background and role. This study discusses the Nuclear proliferation Prevention Act which was proposed recently in the USA. This study suggests policies Korea should take to respond to the changes effectively. (Author)

  18. Study of retrieval, utilize and circulation system for nuclear data in computerized media

    Energy Technology Data Exchange (ETDEWEB)

    Ohbayasi, Yosihide [Hokkaido Univ., Meme Media Laboratory, Sapporo, Hokkaido (Japan)

    2001-03-01

    We have shown and have developed a new type of nuclear data retrieval system, in which a nuclear reaction data compilation is applied as an example. To get benefits from recent computer and network technologies, we adopt the IntelligentPad architecture as a framework of the present system. We set the future aim of our database system toward the 'effective' use of nuclear reaction data: I. 'Re-produce, Re-edit, Re-use', II. 'Circulation, Evolution', III. 'Knowledge discovery'. We discuss the appropriate concepts, which fit for the above purpose. (author)

  19. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1

    International Nuclear Information System (INIS)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety

  20. Study of retrieval, utilize and circulation system for nuclear data in computerized media

    International Nuclear Information System (INIS)

    Ohbayasi, Yosihide

    2001-01-01

    We have shown and have developed a new type of nuclear data retrieval system, in which a nuclear reaction data compilation is applied as an example. To get benefits from recent computer and network technologies, we adopt the IntelligentPad architecture as a framework of the present system. We set the future aim of our database system toward the 'effective' use of nuclear reaction data: I. 'Re-produce, Re-edit, Re-use', II. 'Circulation, Evolution', III. 'Knowledge discovery'. We discuss the appropriate concepts, which fit for the above purpose. (author)

  1. Future perspective of nuclear energy utilization and expected role of HTGR. JAERI's energy systems analysis research

    International Nuclear Information System (INIS)

    Sato, Osamu

    1996-01-01

    Studies have been made in JAERI in order to assess the possibility of using nuclear energy symbiotically with fossil and biomass fuels, and to evaluate its implications for the environment. The application system of high temperature nuclear heat has been designed for this purpose with various technology options. The core of the system is a set of technologies for hydrogen production and its application to produce clean and convenient fuels from fossil or biomass sources. The results of analytical studies using the MARKAL model have indicated sufficient possibilities of combining nuclear energy effectively with fossil or biomass fuels via hydrogen produced by high temperature nuclear heat. In addition to providing clean and convenient liquid fuels on a large scale, the combined system will contribute to the substantial reduction of long-term CO 2 emissions. The relatively high cost of this system will be well justified when CO 2 emission penalties are taken into account. (J.P.N.)

  2. Sharing product data of nuclear power plants across their lifecycles by utilizing a neutral model

    Energy Technology Data Exchange (ETDEWEB)

    Mun, Duhwan [WIG Craft Research Division, Maritime and Ocean Engineering Research Institute, KORDI, 171 Jang-dong, Yuseong-gu, Daejeon 305-343 (Korea, Republic of)], E-mail: dhmun@moeri.re.kr; Hwang, Jinsang [Department of Mechanical Engineering, KAIST (Korea, Republic of)], E-mail: mars@icad.kaist.ac.kr; Han, Soonhung [Department of Mechanical Engineering, KAIST (Korea, Republic of)], E-mail: shhan@kaist.ac.kr; Seki, Hiroshi [Hitachi Research Laboratory, Hitachi, Ltd. (Japan)], E-mail: hiroshi.seki.mf@hitachi.com; Yang, Jeongsam [Industrial and Information Systems Engineering, Ajou University (Korea, Republic of)], E-mail: jyang@ajou.ac.kr

    2008-02-15

    Many public and private Korean organizations are involved during the lifecycle of a domestic nuclear power plant. Korea Plant Engineering Co. (KOPEC) participates in the design stage, Korea Hydraulic and Nuclear Power (KHNP) operates and manages all nuclear power plants in Korea, Doosan Heavy Industry and Construction Co. manufactures the main equipment, and a construction company constructs the plant. Even though each organization has its own digital data management system and obtains a certain level of automation, data sharing among organizations is poor. KHNP obtains drawings and technical specifications from KOPEC in the form of paper. This results in manual re-work of definitions, and errors can potentially occur in the process. In order to establish an information bridge between design and operation and maintenance (O and M) phases, a generic product model (GPM), a data model from Hitachi, is extended for constructing a neutral data warehouse and the Korean Nuclear Power Plant Information Sharing System (KNPISS) is implemented.

  3. Sharing product data of nuclear power plants across their lifecycles by utilizing a neutral model

    International Nuclear Information System (INIS)

    Mun, Duhwan; Hwang, Jinsang; Han, Soonhung; Seki, Hiroshi; Yang, Jeongsam

    2008-01-01

    Many public and private Korean organizations are involved during the lifecycle of a domestic nuclear power plant. Korea Plant Engineering Co. (KOPEC) participates in the design stage, Korea Hydraulic and Nuclear Power (KHNP) operates and manages all nuclear power plants in Korea, Doosan Heavy Industry and Construction Co. manufactures the main equipment, and a construction company constructs the plant. Even though each organization has its own digital data management system and obtains a certain level of automation, data sharing among organizations is poor. KHNP obtains drawings and technical specifications from KOPEC in the form of paper. This results in manual re-work of definitions, and errors can potentially occur in the process. In order to establish an information bridge between design and operation and maintenance (O and M) phases, a generic product model (GPM), a data model from Hitachi, is extended for constructing a neutral data warehouse and the Korean Nuclear Power Plant Information Sharing System (KNPISS) is implemented

  4. Overview of implementing a project control system in the nuclear utility industry

    International Nuclear Information System (INIS)

    Cooprider, D.H.

    1994-01-01

    During the late 1980s, a metamorphosis began at Florida Power and Light Company (FPL). A strategic step in nuclear engineering's efforts to become more cost effective began in January 1990. A project control department was formed. The initial mission was to provide support for nuclear engineering design activities associated with FPL's two twin-unit nuclear power generation facilities - Turkey Point and St. Lucie. Later, the goal expanded to include the division's materials management, nuclear licensing, and information management departments. The project control group was organized along the lines of the organizations served. Separate dedicated groups were established for each plant. Since most engineering activity was based at the Juno Beach headquarters, the project control staff also was based there

  5. Potential utilities of optimal estimation and control in nuclear power plants

    International Nuclear Information System (INIS)

    Tylee, J.L.; Purviance, J.E.

    1983-01-01

    Optimal estimation and control theories offer the potential for more precise control and diagnosis of nuclear power plants. The important element of these theories is that a mathematical plant model is used in conjunction with the actual plant data to optimize some performance criteria. These criteria involve important plant variables and incorporate a sense of the desired plant performance. Several applications of optimal estimation and control to nuclear systems are discussed

  6. Review Article : Utilization of Environmental Radiochemistry Techniques for Selection and Evaluation of Nuclear Facility Sites

    International Nuclear Information System (INIS)

    Atta, E.R.; Madbouly, A.M.; Zakaria, Kh.M.

    2016-01-01

    This research review puts necessary considerations on the available environmental radiochemistry techniques for selection and evaluation of a nuclear facility sites.The main bjective in site evaluation for nuclear facilities in terms of nuclear safety is to protect the site workers, the public and the environment from the effects of ionizing radiation release from nuclear facilities due to accidents. The extreme sensitivity and speed of radiochemical methods make their applications of considerable importance in several fields and they have found many uses. Information about the existed radioactivity in the different nuclear facilities is an essential requirement for their environmental assessment. It is necessary to estimate the various radioactivity levels in the environment through qualitative and quantitative analytical techniques and to assess the potential effects of the nuclear facility in the region by considering the characteristics of sites.The siting and site evaluation requirements are discussed. Emphasis was given to types of radiochemical techniques used for characterization of the site parameters which determine the potential hazards of the site on the facility and the facility on the site. Emphasis has been also given to the quantitative and qualitative analysis of naturally occurring radionuclides for monitoring and control .There are some techniques employed such as radioactive tracer technique, liquid scintillation technique, gamma spectrometry technique, neutron activation analysis technique, fluorimetric technique and isotope hydrology technique.

  7. Research Reactor Utilization at the University of Utah for Nuclear Education, Training and Services

    International Nuclear Information System (INIS)

    Jevremovic, T.; Choe, D.O.

    2013-01-01

    In the years of nuclear renaissance we all recognize a need for modernizing the approaches in fostering nuclear engineering and science knowledge, in strengthening disciplinary depth in students’ education for their preparation for workforce, and in helping them learn how to extend range of skills, develop habits of mind and subject matter knowledge. The education infrastructure at the University of Utah has been recently revised to incorporate the experiential learning using our research reactor as integral part of curriculum, helping therefore that all of our students build sufficient level of nuclear engineering literacy in order to be able to contribute productively to nuclear engineering work force or continue their education toward doctoral degrees. The University of Utah TRIGA Reactor built 35 years ago represents a university wide facility to promote research, education and training, as well as is used for various applications of nuclear engineering, radiation science and health physics. Our curriculum includes two consecutive classes for preparation of our students for research reactor operating license. Every year the US Nuclear Regulatory Commission’s representatives hold the final exam for our students. Our activities serve the academic community of the University of Utah, commercial and government entities, other universities and national laboratories as well. (author)

  8. The service lifetime of Spain's nuclear plants; La vida util de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez-Bolanos, M.

    2008-07-01

    In recent years consideration has been given to the long-term operation of nuclear reactors, beyond their originally foreseen design lifetime. This article analyses the legal and safety requirements that this implies, in the wake of the document dealing with this issue that was approved by the Plenary of the CSN in April 2005. The article is completed with an interview with Dale Klein, president of the United States regulatory body, in which he describes the experience accumulated in his country, where lifetime extensions have already been approved for 50 plants. (Author)

  9. West Valley Demonstration Project facilities utilization plan for the existing facilities at the Western New York Nuclear Service Center

    International Nuclear Information System (INIS)

    Skillern, C.G.

    1986-05-01

    In 1980, Congress passed Public Law 96-368, the West Valley Demonstration Project (WVDP) Act. As a primary objective, the Act authorized the US Department of Energy (DOE) to solidify the high-level waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC) into a form suitable for transportation and disposal in a federal repository. This report will describe how WVDP proposes to use the existing WNYNSC Facilities in an efficient and technically effective manner to comply with Public Law 96-368. In support of the above cited law, the DOE has entered into a ''Cooperative agreement between the United States Department of Energy and the New York State Energy Research and Development Authority on the Western New York Nuclear Service Center at West Valley, New York.'' The state-owned areas turned over to the DOE for use are as follows: Process Plant, Waste Storage, Low-Level Waste Treatment Facility, Service Facilities, Plant Security, and Additional Facilities. The Facilities Utilization Plan (FUP) describes how the state-owned facilities will be utilized to complete the Project; it is divided into five sections as follows: Executive Summary - an overview; Introduction - the WVDP approach to utilizing the WNYNSC Facilities; WVDP Systems - a brief functional description of the system, list of equipment and components to be used and decontamination and decommissioning (D and D) support; WVDP Support Facilities; and Caveats that could effect or change the potential usage of a particular area

  10. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1992

    International Nuclear Information System (INIS)

    1993-08-01

    The results of the joint researches by utilizing the facilities of JAERI in 1992 fiscal year were summarized. The number of research themes in 1992 was 247 cases. In this book, 166 reports are collected. (J.P.N.)

  11. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1993

    International Nuclear Information System (INIS)

    1994-07-01

    The results of the joint researches by utilizing the facilities of JAERI in 1993 fiscal year were summarized. The number of research themes in 1993 was 228 cases. In this book, 243 reports are collected. (J.P.N.)

  12. Utilization of the IPR-RI research nuclear reactor in evaluation of Brazilian uranium reserves

    International Nuclear Information System (INIS)

    Carvalho Tofani, P. de; Stasiulevicius, R.

    1984-01-01

    Analytical techniques which were developed utilizing the IPR-R1 research reactor, are presented. These techniques determined the uranium contents and other chemical elements for several samples gathered in all national territory. (M.C.K) [pt

  13. Surveillance and analysis of nuclear R and D manpower for efficient utilization of KAERI's nuclear R and D resources

    International Nuclear Information System (INIS)

    Kim, Hyun Jun; Yang, M. H.; Song, K. D.; Chung, W. S.; Yun, S. W.; Won, B. C.; Yoon, H. M.

    1999-11-01

    This study aimed at securing row data on KAERI's manpower resources, which be useful to establish the short and long term R and D policy of KAERI. To coincide with the objectives, this study covered following scopes; (1) identification of status and issues of manpower in science and technology fields, (2) identification of status and issues of KAERI's manpower management policy, (3) gathering row data on KAERI's manpower through surveillance and analysis, and analyzing staff's perception on KAERI's manpower utilization policy, (4) suggestion of short and long term policy direction of manpower management of KAERI. (author)

  14. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal, 1991

    International Nuclear Information System (INIS)

    1992-08-01

    The results of the joint researches by utilizing the facilities of JAERI in 1991 fiscal year were summarized, and this report was able to be completed. Many researchers in whole Japan took part in many themes, and the very significant results were obtained. Now this joint research has reached the great turnabout period. The reconstructed JRR-3M was offered for joint utilization since April, 1991, and the utilization for neutron diffraction and scattering increased largely. As for the ion irradiation facility in Takasaki Research Establishment, the partial operation will be started in the next year, and the joint utilization is expected to begin. Accompanying the diversification of the utilization of facilities, in order to properly meet the needs of users, the thorough revision of the system seems necessary. The number of research themes in 1991 was 222 cases. JRR-3M accomplished the joint utilization operation of 8 cycles as expected, but JRR-2 caused a trouble during 5th cycle, and the operation thereafter was canceled. In this book, 159 reports are collected. (K.I.)

  15. Report on results of utilizing nuclear reactor, April, 1983 - March, 1984

    International Nuclear Information System (INIS)

    1984-01-01

    The reactor in the Institute for Atomic Energy, Rikkyo University, is usually operated for 6 hours a day. It has been operated for 21 years without large trouble. The time of operation in fiscal year 1983 was 551 hours, and the cumulative power output was 47,511 kWh. From December, 1983, to March, 1984, the reactor was shut down, and the repair works for the secondary cooling system were carried out, accordingly, the power output and the number of utilization cases decreased. The total number of utilization cases in fiscal year 1983 was 2,702, and the total time of utilization was 8,497 hr 26 min. The utilization by universities accounted for 53.8%. A short period course was held as usual to educate and train 14 students. The radiation control for individuals and controlled areas is reported. The management of solid, gas end liquid wastes and their amounts being preserved in the Institute are reported. The radioactivity in environmental samples was measured 4 times in a year by total beta method, and the data on soil, sea bottom sediment, seawater and marine products are given. The summary of the research made by the personnel of the Institute and other achievement are also described. The execution of research in 1983 owed largely to the scientific research promotion fund of Japan Private School Promotion Foundation. The reactor was effectively utilized by the common utilization of the Rikkyo reactor. (Kako, I.)

  16. International topical meeting on nuclear research applications and utilization of accelerators. Book of abstracts

    International Nuclear Information System (INIS)

    2009-01-01

    Applications of particle accelerators cover a number of areas, from strategic and applied research, safety and security, environmental applications, materials research and analytical sciences, to radioisotope production and radiation processing. Accelerator based techniques and pulsed neutron sources are expected to lead to new initiatives in materials research of relevance for both the nuclear and non-nuclear fields. Material science studies with the use of accelerators, neutron beams and other nuclear analytical methods are relevant to the development of advanced reactors, nuclear fuel cycle needs and fusion research. In this regard, a better understanding of the irradiation effects in materials for energy and non-energy applications is needed, and is reflected in accelerator techniques for modification and analysis of materials for nuclear technologies. Accelerator applications for innovative nuclear systems aiming at rad-waste transmutation (e.g., accelerator driven systems) are being pursued in many countries. Research and development using accelerators involves a broad spectrum of skills to build a cadre of trained experts in nuclear techniques in IAEA Member States, and to generate knowledge for innovative methodologies and tools. The present conference is also being held in cooperation with the American Nuclear Society (ANS), which successfully organized the series of accelerator applications conferences known as AccApp. The ANS series of topical meetings has provided a forum for the global exchange of scientific and technical knowledge on a wide variety of related topics since the first AccApp took place in 1997 in Albuquerque, USA. The last conference which was held in 2007 in Pocatello, USA, was jointly organized by the ANS and the IAEA. The main objectives of the conference are to promote exchange of information among IAEA Member States representatives/delegates and to discuss new trends in accelerator applications including nuclear materials research

  17. The nuclear regulatory body and the principles of utility, legality and legitimacy

    International Nuclear Information System (INIS)

    Wieland, Patricia; Almeida, Ivan P. Salati de; Almeida, Claudio Ubirajara

    2007-01-01

    The nuclear regulation is justified by the principles of usefulness, legality and legitimacy. Usefulness is defined as the value that regulation adds to the society; legality is when the society manifests its will for regulation and this is done by the laws, establishing the regulatory body scope and responsibilities. Legitimacy is the less evident concept, as it depends more on the public perception and acceptance than on any other parameter. The nuclear regulator credibility depends basically on its autonomy and independence to make decisions. The challenge is to keep neutrality against political and industrial interests and to overcome difficulties such as the lack of objectivity and criteria, lack of specific competence and excess of dependence in individual decisions. This paper deals with the effectiveness of nuclear regulatory bodies and proposes a basic structure of an ideal management model. (author)

  18. Legal aspects of nuclear power production and utilization in the USSR

    International Nuclear Information System (INIS)

    Iojrysh, A.I.; Supataeva, O.A.

    1986-01-01

    The history and prospects of development of nuclear power engineering in the USSR are considered. The problems of establishment and development of the atomic energy law are discussed. The general characteristics of the atomic energy legislation are given. The principal problem of the atomic energy law is the development of the mechanism fo nuclear power engineering management able to provide protection of people life, health and property. Peaceful use of nuclear energy is the basic principle of the Soviet atomic energy law. Departamental acts are the main sources of atomic energy legislation. Ordering of legislation, its systematization, approval of a complex standard act being the Soviet atomic energy law will result in completing the formation of a new complex branch of soviet legislation namely, the atomic energy law

  19. Utilization of niching methods of genetic algorithms in nuclear reactor problems optimization

    International Nuclear Information System (INIS)

    Sacco, Wagner Figueiredo; Schirru, Roberto

    2000-01-01

    Genetic Algorithms (GAs) are biologically motivated adaptive systems which have been used, with good results, in function optimization. However, traditional GAs rapidly push an artificial population toward convergence. That is, all individuals in the population soon become nearly identical. Niching Methods allow genetic algorithms to maintain a population of diverse individuals. GAs that incorporate these methods are capable of locating multiple, optimal solutions within a single population. The purpose of this study is to test existing niching techniques and two methods introduced herein, bearing in mind their eventual application in nuclear reactor related problems, specially the nuclear reactor core reload one, which has multiple solutions. Tests are performed using widely known test functions and their results show that the new methods are quite promising, specially in real world problems like the nuclear reactor core reload. (author)

  20. Evaluation of utilizing spent fuel and plutonium by optimization model for nuclear fuel cycle

    International Nuclear Information System (INIS)

    Yoshida, Naoto; Fujii, Yasumasa; Komiyama, Ryoichi

    2016-01-01

    The nuclear power generation has played an important role in power generation mix as a base load power supply. On the other hand, increasing spent fuel and separated plutonium is a long-standing problem. It is expected that advanced fast reactor and high temperature gas reactor could reduce nuclear waste and effectively consume it as valuable resources. Specific scenarios about spent fuel and the gross weight of plutonium are assumed in this study, and the installable potential of fuel cycle and the most suitable reactor mix are analyzed. The model is formulated as liner programing. The model identifies the best strategy of mix of nuclear reactor types to minimize the present value of total cost in a forecast period. As a result, Fast Breeder Reactor and High Temperature Gas Reactor reduce stored spent fuel and increase the consumptions of plutonium. (author)

  1. Analysis on misconducts and inappropriate practices by Japan's Nuclear Power Utilities and Assessment of their corrective measures

    International Nuclear Information System (INIS)

    Torikai, Seishi; Ozawa, Michihiro; Kanegae, Naomichi; Tani, Masaaki; Miyakoshi, Naoki; Madarame, Haruki

    2010-01-01

    On March 30, 2007, Japan's electric utilities reported the results of a complete review of their powergenerating units to the Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade, and Industry (METI). The Ethics Committee of the Atomic Energy Society of Japan (AESJ) then recommended an assessment method to analyze the seriousness of the problems from multiple perspectives in order to support the public's understanding of the reported problems. Accordingly, the Ethics Committee conducted the assessment. The assessment considered each reported problem associated with nuclear power-generating units and the preventive measures completed between June 2007 and September 2008 (corrective measures continued beyond that period). The results were presented at the autumn conferences of AESJ in 2007 and 2008, and are discussed in this report. (author)

  2. Utilization of cross-section covariance data in FBR core nuclear design and cross-section adjustment

    International Nuclear Information System (INIS)

    Ishikawa, Makoto

    1994-01-01

    In the core design of large fast breeder reactors (FBRs), it is essentially important to improve the prediction accuracy of nuclear characteristics from the viewpoint of both reducing cost and insuring reliability of the plant. The cross-section errors, that is, covariance data are one of the most dominant sources for the prediction uncertainty of the core parameters, therefore, quantitative evaluation of covariance data is indispensable for FBR core design. The first objective of the present paper is to introduce how the cross-section covariance data are utilized in the FBR core nuclear design works. The second is to delineate the cross-section adjustment study and its application to an FBR design, because this improved design method markedly enhances the needs and importance of the cross-section covariance data. (author)

  3. Results from the second Galaxy Serpent web-based table top exercise utilizing the concept of nuclear forensics libraries

    International Nuclear Information System (INIS)

    Borgardt, James; Canaday, Jodi; Chamberlain, David

    2017-01-01

    Galaxy Serpent is a unique, virtual, web-based international tabletop series of exercises designed to mature the concept of National Nuclear Forensics Libraries (NNFLs). Teams participating in the second version of the exercise were provided synthetic sealed radioactive source data used to compile a model NNFL which then served as a comparative instrument in hypothetical scenarios involving sources out of regulatory control, allowing teams to successfully down-select and determine whether investigated sources were consistent with holdings in their model library. The methodologies utilized and aggregate results of the exercise will be presented, along with challenges encountered and benefits realized. (author)

  4. Utilization technique of 'radiation management manual in medical field (2012).' What should be learnt from the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Kikuchi, Toru

    2014-01-01

    From the abstract of contents of the 'Radiation management manual in medical field (2012),' the utilization technique of the manual is introduced. Introduced items are as follows: (1) Exposure management; exposure management for radiation medical workers, patients, and citizens in the medical field, and exposure management for radiation workers and citizens involved in the emergency work related to the Fukushima nuclear accident, (2) Health management; health management for radiation medical workers, (3) Radiation education: Education/training for radiation medical workers, and radiation education for health care workers, (4) Accident and emergency measures; emergency actions involved in the radiation accidents and radiation medicine at medical facilities

  5. A new era in nuclear energy science. When will radiation application receive citizenship ranking along with energy utilization

    International Nuclear Information System (INIS)

    Tabata, Yoneho; Tagawa, Seiichi; Saito, Naoki; Fujii, Yasuhiko

    2005-01-01

    Japan has been obtaining definite results in these decades in both fields of nuclear power generation (energy utilization) and radiation application thus contributing to a sustainable development of the world. The present special issue of 'Atom Eye' introduces (1) Japanese achievements in cooperative relationships with developing countries in the field of radiation applications, (2) history of research and development of radiation-utilization techniques in Japan, (3) present status of quantum-beam applications in life-science, medial application, and nano-technology, etc, (4) applications of high-intensity neutron source, (5) cancer therapy using high-energy heavy-ion beams, (6) radiation sterilizations, (7) radiation mutations, (8) three interviewer's reports visiting several research institutes of radiation applications in Japan, and introduction of (9) a bencher enterprise and also (10) an accelerator business. (S. Ohno)

  6. The study on the role of very high temperature reactor and nuclear process heat utilization in future energy systems

    International Nuclear Information System (INIS)

    Yasukawa, Sigeru; Mankin, Shuichi; Tadokoro, Yoshihiro; Sato, Osamu; Yamaguchi, Kazuo; Ueno, Seiichi

    1986-11-01

    This report describes the analytical results being made in the study on the role of Very High Temperature Reactor and nuclear process heat utilization in future energy system, which is aimed at zero emission. In the former part of the report, the modeling of the reference energy system, main characteristics of energy technologies, and scenario indicators as well as system behavioral objectives for optimization are explained. In the latter part, analytical results such as the time-period variation of overall energy utilization efficiency, energy supply/demand structure in long-terms, energy contribution and economic competition of new energy technologies, environmental effluents released through verious energy activities, impacts to and from national economy, and some sensitivity analyses, are reviewed. (author)

  7. A utilization of fuzzy control for design automation of nuclear structures

    International Nuclear Information System (INIS)

    Yoshimura, Shinobu; Yagawa, Genki; Mochizuki, Yoshihiko

    1991-01-01

    This paper describes an automated design of nuclear structures by means of some artificial intelligence techniques. The 'generate and test' strategy is adopted as a basic strategy of design. An empirical approach with the fuzzy control is introduced for efficient design modification. This system is applied to the design of some 2D models of the fusion first wall. (author)

  8. Reactor waste heat utilization and district heating reactors. Nuclear district heating in Sweden - Regional reject heat utilization schemes and small heat-only reactors

    International Nuclear Information System (INIS)

    Hannerz, K.; Larsson, Y.; Margen, P.

    1977-01-01

    A brief review is given of the current status of district heating in Sweden. In future, district heating schemes will become increasingly interesting as a means of utilizing heat from nuclear reactors. Present recommendations in Sweden are that large reactors should not be located closer than about 20 km from large population centres. Reject heat from such reactors is cheap at source. To minimize the cost of long distance hot water transmission large heat rates must be transmitted. Only areas with large populations can meet this requirement. The three areas of main interest are Malmoe/Lund/Helsingborg housing close to 0.5 million; Greater Stockholm housing 1 to 1.5 million and Greater Gothenburg housing about 0.5 million people. There is an active proposal that the Malmoe/Lund/Helsingborg region would be served by a third nuclear unit at Barsebaeck, located about 20 km from Malmoe/Lund and supplying 950 MW of base load heat. Preliminary proposals for Stockholm involve a 2000 MW heat supply; proposals for Gothenburg are more tentative. The paper describes progress on these proposals and their technology. It also outlines technology under development to increase the economic range of large scale heat transport and to make distribution economic even for low heat-density family housing estates. Regions apart from the few major urban areas mentioned above require the adoption of a different approach. To this end the development of a small, simple low-temperature reactor for heat-only production suitable for urban location has been started in Sweden in close contact with Finland. Some results of the work in progress are presented, with emphasis on the safety requirements. An outline is given in the paper as to how problems of regional heat planning and institutional and legislative issues are being approached

  9. The self-consistent energy system with an enhanced non-proliferated core concept for global nuclear energy utilization

    International Nuclear Information System (INIS)

    Kawashima, Masatoshi; Arie, Kazuo; Araki, Yoshio; Sato, Mitsuyoshi; Mori, Kenji; Nakayama, Yoshiyuki; Nakazono, Ryuichi; Kuroda, Yuji; Ishiguma, Kazuo; Fujii-e, Yoichi

    2008-01-01

    A sustainable nuclear energy system was developed based on the concept of Self-Consistent Nuclear Energy System (SCNES). Our study that trans-uranium (TRU) metallic fuel fast reactor cycle coupled with recycling of five long-lived fission products (LLFP) as well as actinides is the most promising system for the sustainable nuclear utilization. Efficient utilization of uranium-238 through the SCNES concept opens the doors to prolong the lifetime of nuclear energy systems towards several tens of thousand years. Recent evolution of the concept revealed compatibility of fuel sustainability, minor actinide (MA) minimization and non-proliferation aspects for peaceful use of nuclear energy systems through the discussion. As for those TRU compositions stabilized under fast neutron spectra, plutonium isotope fractions are remained in the range of reactor grade classification with high fraction of Pu240 isotope. Recent evolution of the SCNES concept has revealed that TRU recycling can cope with enhancing non-proliferation efforts in peaceful use with the 'no-blanket and multi-zoning core' concept. Therefore, the realization of SCNES is most important. In addition, along the process to the goals, a three-step approach is proposed to solve concurrent problems raised in the LWR systems. We discussed possible roles and contribution to the near future demand along worldwide expansion of LWR capacities by applying the 1st generation SCNES. MA fractions in TRU are more than 10% from LWR discharged fuels and even higher up to 20% in fuels from long interim storages. TRU recycling in the 1st generation SCNES system can reduce the MA fractions down to 4-5% in a few decades. This capability significantly releases 'MA' pressures in down-stream of LWR systems. Current efforts for enhancing capabilities for energy generation by LWR systems are efficient against the global warming crisis. In parallel to those movements, early realization of the SCNES concept can be the most viable decision

  10. Barnwell Nuclear Fuels Plant applicability study. Volume II. BNFP: utilization alternatives, evaluations, and conclusions

    International Nuclear Information System (INIS)

    1978-04-01

    Descriptions and status of the Barnwell separations facility and related fuel cycle facilities are given. Alternative uses other than reprocessing, evaluation of uses for reprocessing alternatives, resource utilization and its relationship to U.S. security objectives, and evaluation of ownership-management options are discussed

  11. Northwest power gamble: Washington utilities go for broke on nuclear; region's citizens make conservation bid

    International Nuclear Information System (INIS)

    Brummer, J.

    1981-01-01

    The Washington Public Power Supply System (WPPSS) is asking for a reactor construction moratorium in an effort to get fast relief from the Bonneville Power Administration (BPA), which is authorized to guarantee power purchases from new power plants. Supporters of nuclear power plants as well as those of the soft energy path are watching to see how BPA will handle its mandate against acquiring new thermal plants until conservation and renewable energy potentials are exhausted. BPA can subvert the Pacific Northwest Power Act with 20-year contracts based on conventional forecasts despite evidence that new plants are unneeded. There is also evidence that the public rejects the idea of a moral obligation to bail out nuclear power cost overruns at taxpayer expense. The negotiations involve not only WPPSS and BPA, but Moody's Investor Service and environmental groups

  12. Review of the utilization of laser and electron beam methods in the nuclear domain

    International Nuclear Information System (INIS)

    Charissoux, C.; Bonnin, P.; Calvet, J.N.; Contre, M.

    1987-01-01

    The use of laser and electron beams by the nuclear industry for making components, fabricating fuels, waste processing, maintenance, and dismantling installations is reviewed. The advantages in welding include very rapid thermal cycles, deep weld zones with a restricted effect on surrounding material, and reduced residual stress. Surface treatments can also take advantage of these benefits. In cutting, the intrinsic advantages of the laser are completed by its high potential for robotization [fr

  13. Economic considerations of plutonium utilization in the nuclear power strategy of Finland

    International Nuclear Information System (INIS)

    Silvennoinen, P.; Tusa, E.; Routti, J.T.

    1977-01-01

    Based on the current and prospected share of nuclear power in the national energy supply strategy an optimal programme is developed for exploitation of plutonium in both light water and fast reactor systems. Assuming cost trends until and beyond the year 2000 for uranium, plutonium, uranium enrichment, fuel fabricaton and assessing the availability of plutonium from the domestic power plants and from abroad the nuclear construction programme is optimized economically in view of the estimated development in the investment costs of various plant types. Given the expected nuclear share of the energy procurement this sector is covered by the alternative production schemes, i.e. light water reactors with and without plutonium recycle and fast reactors. The plant sizes are allowed to be either 500 MWe or 1000 MWe. The installation dates are fixed manually with a minor flexibility of time but with all the three degrees of freedom in the plant types. Defining the objective function in terms of minimized revenue requirement in plant amortization and operation the generated scenarios are screened off and they finally converge to the optimal policy of nuclear power construction up to the year 2000. Special attention is placed on the constraints which eliminate excessive proliferation of reactor types. This is mainly implemented by the criterion of increasing the domestic share in the investments. The established technology is associated with a larger share of the Finnish manufacturing and the introduction of new fuel or reactor type is taken to correspond to a reduced domestic investment share. The results yield the time schedule and installed capacity of the three different production means. Due to the uncertainties prevailing in the forecasts sensitivity studies are performed as functions of the major economic parameters and their temporal development

  14. Economic considerations of plutonium utilization in the nuclear power strategy of Finland

    International Nuclear Information System (INIS)

    Silvennoinen, P.; Tusa, E.; Routti, J.T.

    1977-01-01

    Based on the current and predicted share of nuclear power in the national energy supply strategy, an optimal programme is developed for the exploitation of plutonium in both light-water and fast reactor systems. Assuming cost trends beyond the year 2000 for uranium, plutonium, uranium enrichment, fuel fabrication and assessing the availability of plutonium from domestic power plants and from abroad, the nuclear construction programme is optimized economically in view of the estimated development in the investment costs of various plant types. Given the expected nuclear share of the energy procurement this sector is covered by the alternative production schemes, i.e. light-water reactors with and without plutonium recycle, and fast reactors. Defining the objective function in terms of minimized revenue requirement in plant amortization and operation the generated scenarios are screened off and they finally converge to the optimal policy of nuclear power construction up to the year 2000. The established technology is associated with a larger share of the domestic manufacturing and the introduction of a new fuel or reactor type is taken to correspond to a reduced domestic investment share. In the investment costs the domestic fraction is regarded competitive up to a certain marginal excess. Plutonium recycle is seen to be competitive from 1985 or as soon as the required amount of fuel has been reprocessed. The domestic accumulation of plutonium will be able to support the introduction of the LMFBR in 1997. Owing to the uncertainties prevailing in the forecasts, sensitivity studies are performed as functions of the major economic parameters and their temporal development. (author)

  15. Nuclear power investment and generating costs from a utility point of view

    International Nuclear Information System (INIS)

    Roth, B.F.

    1975-01-01

    Nuclear power stations presently in operation in the Federal Republic of Germany have electricity generating costs between 3.5 Pf/kWh and 4.5 Pf/kWh. The higher electricity generating costs are due mainly to the increased expenditure required for the protection of plants against airplane crashes, earthquakes and sabotage, and to the higher costs of the entire fuel cycle. (orig./RW) [de

  16. Zero Quantum Nuclear Magnetic Resonance experiments utilizing a toroid cell and coil

    OpenAIRE

    Bebout, William Roach

    1989-01-01

    Over the past ten to fifteen years the area of Nuclear Magnetic Resonance (NMR) Spectroscopy has seen tremendous growth. For example, in conjunction with multiple quantum NMR, molecular structural mapping of a compound can be easily performed in a two dimensional (2D) experiment. However, only two kinds of detector coils have been typically used in NMR studies. These are the solenoid coil and the Helmholtz coil. The solenoid coil was very popular with the permanent and e...

  17. Utilization of carbon/carbon composites in nuclear simulation fuel rods

    International Nuclear Information System (INIS)

    Polidoro, H.A.; Otani, S.; Rezende, M.C.; Ferreira, S.R.; Otani, C.

    1988-01-01

    Thermo-hydraulic problems, in nuclear plants are normally analysed by using electrically heated rods. Carbon/carbon composites were used to make heating elements for testing by indirect heating up to a heat flux of 100 W/cm 2 . It is easy to verify that this value can be exceed if the choice of the complementary materials for insulator and cladding were improved. The swaging process used to reduce the cladding diameter prevented the fabrication of graphite heater rods. (author) [pt

  18. Utility of Characterizing and Monitoring Suspected Underground Nuclear Sites with VideoSAR

    Science.gov (United States)

    Dauphin, S. M.; Yocky, D. A.; Riley, R.; Calloway, T. M.; Wahl, D. E.

    2016-12-01

    Sandia National Laboratories proposed using airborne synthetic aperture RADAR (SAR) collected in VideoSAR mode to characterize the Underground Nuclear Explosion Signature Experiment (UNESE) test bed site at the Nevada National Security Site (NNSS). The SNL SAR collected airborne, Ku-band (16.8 GHz center frequency), 0.2032 meter ground resolution over NNSS in August 2014 and X-band (9.6 GHz), 0.1016 meter ground resolution fully-polarimetric SAR in April 2015. This paper reports the findings of processing and exploiting VideoSAR for creating digital elevation maps, detecting cultural artifacts and exploiting full-circle polarimetric signatures. VideoSAR collects a continuous circle of phase history data, therefore, imagery can be formed over the 360-degrees of the site. Since the Ku-band VideoSAR had two antennas suitable for interferometric digital elevation mapping (DEM), DEMs could be generated over numerous aspect angles, filling in holes created by targets with height by imaging from all sides. Also, since the X-band VideoSAR was fully-polarimetric, scattering signatures could be gleaned from all angles also. Both of these collections can be used to find man-made objects and changes in elevation that might indicate testing activities. VideoSAR provides a unique, coherent measure of ground objects allowing one to create accurate DEMS, locate man-made objects, and identify scattering signatures via polarimetric exploitation. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. The authors would like to thank the National Nuclear Security Administration, Defense Nuclear Nonproliferation Research and Development, for sponsoring this work. We would also like to thank the Underground Nuclear Explosion Signatures Experiment team, a multi

  19. The utility of N-15 nuclear magnetic resonance spectroscopy for the study of natural products

    International Nuclear Information System (INIS)

    Randall, E.W.

    1978-01-01

    The utility of 15 N NMR spectroscopy for the study of natural products and the difficulties which must be overcome arte discussed. The widespread use of pulse Fourier techniques, decouplings, larger magnetic fields and large tube sizes allows a large number of 15 N studies of natural products, the more recent and important of these being peptides, nucleosides and nucleotides. Sites of protonation, tautomerism, sites of nitrosation and proton exchange behaviour for some of these natrual products have been studied. (A.G.)

  20. Perspectives of nuclear power in the UK - the view of a utility

    International Nuclear Information System (INIS)

    Golby, P.

    2007-01-01

    Nuclear energy is back on the agenda in UK due to the discussion about climate change and security of supply. First, the UK has to face up to the challenges of reducing its greenhouse gas emissions. The UK Government has adopted a clear leadership position on climate change internationally. Second, UK is facing some fundamental questions about the future security of the energy supplies. The decline of UKs' gas reserves in the North Sea is bringing to an end the years in which the UK could afford to be relatively relaxed energy and energy policy almost took care of itself. We are expecting the next major milestone with the UK Government due to publish an 'Energy Withe Paper'. Alongside that document they are also due to launch a new consultation on nuclear power and whether it should have a role in the UK market. For investment in nuclear to be a credible economic option for investors a number of issues will need to be addressed by the UK Government. These issues include the public and political acceptance, the management of the waste by the Government, and an efficient regulatory and licensing framework for new plants. Two words should be addressed to the UK Government at the moment - urgency and partnership. Urgency - because we desperately need to see progress on energy policy over the next 12 months. It is 5 minutes to midnight and the clock is ticking. Partnership - because investors are ready to make the necessary investments but we need in the UK the long-term policy framework that will underpin and support the scale of the investment we need to see. (orig.)

  1. Electric utilities deregulation and its impact on nuclear power generating stations

    International Nuclear Information System (INIS)

    Trehan, N.K.

    1998-01-01

    Under restructuring and deregulation, it is not clear as to who would have the responsibility, and what obligations the market participants would have to ensure that the electrical system reliability (stability) is maintained. Due to the dynamic nature of the electrical grid, especially with the implementation of restructuring and deregulation, vulnerabilities exist which may impact the reliability (stability) of the offsite electrical power system. In a nuclear power generating unit, an offsite electric power system and an onsite electric power system are required to permit the functioning of structures, systems, and components which are important to safety. The safety function for each system is to provide sufficient capacity and capability to assure that the containment integrity is maintained during power operation or in the event of a postulated accident. Analyses performed by the applicants must verify that the electrical grid remains stable in the event of a loss of the nuclear unit generator, the largest other unit on the grid or the most critical transmission line. The stability of the electric grid is assumed in the safety analyses and a change in it would impact those analyses. However, it may impact the availability of a stable electric power to the safety buses because of the limited number of available transmission lines. This paper discusses electrical power generation and demand, reserve margins, power transfer capability, development of new innovative technologies to compensate for lack of the construction of transmission lines, legislation for the formulation of a self regulation organization (SRO), grid disturbances that may lead to a voltage collapse, and the vulnerabilities which may impact the availability of a stable power to the nuclear power generating stations

  2. Production of synthesis gas and methane via coal gasification utilizing nuclear heat

    International Nuclear Information System (INIS)

    van Heek, K.H.; Juentgen, H.

    1982-01-01

    The steam gasificaton of coal requires a large amount of energy for endothermic gasification, as well as for production and heating of the steam and for electricity generation. In hydrogasification processes, heat is required primarily for the production of hydrogen and for preheating the reactants. Current developments in nuclear energy enable a gas cooled high temperature nuclear reactor (HTR) to be the energy source, the heat produced being withdrawn from the system by means of a helium loop. There is a prospect of converting coal, in optimal yield, into a commercial gas by employing the process heat from a gas-cooled HTR. The advantages of this process are: (1) conservation of coal reserves via more efficient gas production; (2) because of this coal conservation, there are lower emissions, especially of CO 2 , but also of dust, SO 2 , NO/sub x/, and other harmful substances; (3) process engineering advantages, such as omission of an oxygen plant and reduction in the number of gas scrubbers; (4) lower gas manufacturing costs compared to conventional processes. The main problems involved in using nuclear energy for the industrial gasification of coal are: (1) development of HTRs with helium outlet temperatures of at least 950 0 C; (2) heat transfer from the core of the reactor to the gas generator, methane reforming oven, or heater for the hydrogenation gas; (3) development of a suitable allothermal gas generator for the steam gasification; and (4) development of a helium-heated methane reforming oven and adaption of the hydrogasification process for operation in combination with the reactor. In summary, processes for gasifying coal that employ heat from an HTR have good economic and technical prospects of being realized in the future. However, time will be required for research and development before industrial application can take place. 23 figures, 4 tables. (DP)

  3. Utilization of pneumatic energy in industries and Nuclear Energy Unit - a brief review

    International Nuclear Information System (INIS)

    Muhd Noor Muhd Yunus

    1984-01-01

    The purpose of this paper is to evaluate the extent of utilisation of pneumatic energy in UTN, besides depicting the capabilities of pneumatics in various field, especially in nuclear industry. Thus, a few examples of the usage of this energy in industry and UTN are explained and listed briefly. Comparisons and advantages of the pneumatics with respect to other forms of energy also discussed briefly. It is hoped that this pneumatic technology will advanced in UTN and becoming one of the alternatives of offered apart from other form of energy like hyrdaulics and electricity. (author)

  4. An example of the utilization of the military nuclear complex of peaceful purposes

    International Nuclear Information System (INIS)

    Zaleski, P.

    1994-01-01

    One of the major difficulties in military conversion is to find cases that are realistic from the point of view of politics, economics, financing and society. This report proposes an example which is believed to meet the above criteria. The suggestion is to use manpower, and to some extent the installations (laboratories, factories) of Russian military nuclear complex to build a small series of fast neutron plutonium storage reactor power plants. These plants with a unit output of some 800 MWe would have two main functions: store the excess of Russian military grade plutonium and produce electricity at competitive prices

  5. Implementation of the utilization program for the fuel elements of the Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    Martin, H.R.; Serra, O.H.; Parker, Alejandro

    1981-01-01

    The programming operation for the use of the fuel elements in the Atucha-1 nuclear power plant was initially under the responsibility of the KWU Company, as part of the services rendered due for the manufacturing of said elements. This job was done with the help of the TRISIC program, developed in the early seventies by CNEA and SIEMENS staff. From april 21, 1979 on, CNEA took over the responsibility and strategy of the interchange of fuel elements. The several stages carried out for the implementation of this service are detailed. (M.E.L.) [es

  6. A Quantitative Analysis of the Reversibility of Nuclear Waste Storage: Waste Re-utilization

    International Nuclear Information System (INIS)

    Gollier, Christian; Devezeaux de Lavergne, Jean-Guy

    2001-01-01

    The reversibility of nuclear waste storage can be justified on various economic grounds, including the eventuality that future generations may wish to recover this waste in order to re-utilise it. Real options theory is used to cost this option. By including the value of this option in the cost/benefit analysis, it is possible to determine what present generations should spend to organise this reversibility. Taking current values of the materials contained in the waste, and taking into account the low growth trend of such values, we show that the reversibility value of a waste storage site is derisory

  7. Constitutional questions concerning the termination of nuclear energy utilization. The 13th law on the amendment of the atomic law in the frame of basic rights

    International Nuclear Information System (INIS)

    Wieland, Joachim

    2013-01-01

    The nuclear power phaseout in consequence of the nuclear disaster in Fukushima destroyed the expectation of high profits for the NPP owners based on the enacted lifetime extension. Neither professional freedom, nor the principle of property conservation, nor the rule of equality is violated by the termination of nuclear power utilization. The legislative authority was permitted to reverse the decision on the nuclear power utilization towards phaseout. The legislator could invoke its dynamic constitutional obligation for protection of life and physical integrity of the society. The legislator allows the operation of nuclear power plants only if according to the status of science and technology failures that could endanger life and health can practically be excluded. In consequence of the catastrophic accident in Fukushima hazards due to targeted airplane crashes could not be ruled out anymore.

  8. Method of decommissioning nuclear reactor building by utilizing sea water buyoancy

    International Nuclear Information System (INIS)

    Iwashima, Sumio; Ogoshi, Shigeru; Kobari, Shin-ichi.

    1989-01-01

    Upon dismantling nuclear reactor buildings, peripheral yards are excavated and channels leading to sea shore are formed. Since the outer walls of the reactor buildings are made of iron-reinforced concretes, the opening poritons are grouted with concretes to attain a tightly such closed structure that radioactive wastes, etc. in the inside are not flown out upon reactor discommisioning. Peripheral buildings at relatively low level of radiation contaminations are dismantled and withdrawn. The fundations of the nuclear reactor buildings were dug out and jacked to separate base rocks and the reactor buildings. Then, sea water is introduced into the water channels to entirely float up the buildings. A water gate is disposed in the water channel on the side of sea shore to control the level of sea water. The buildings are moved and guided to the sea shore and towed to a site optimum as a permanent storage area and then burried in that place. The operation period for the discommissioning work can greatly be shortened and the radiation dose and the amount of the wastes can be reduced. (T.M.)

  9. The engineering of a nuclear thermal landing and ascent vehicle utilizing indigenous Martian propellant

    International Nuclear Information System (INIS)

    Zubrin, R.M.

    1991-01-01

    The following paper reports on a design study of a novel space transportation concept known as a ''NIMF'' (Nuclear rocket using Indigenous Martian Fuel.) The NIMF is a ballistic vehicle which obtains its propellant out of the Martian air by compression and liquefaction of atmospheric CO 2 . This propellant is subsequently used to generate rocket thrust at a specific impulse of 264 s by being heated to high temperature (2800 K) gas in the NIMFs' nuclear thermal rocket engines. The vehicle is designed to provide surface to orbit and surface to surface transportation, as well as housing, for a crew of three astronauts. It is capable of refueling itself for a flight to its maximum orbit in less than 50 days. The ballistic NIMF has a mass of 44.7 tonnes and, with the assumed 2800 K propellant temperature, is capable of attaining highly energetic (250 km by 34000 km elliptical) orbits. This allows it to rendezvous with interplanetary transfer vehicles which are only very loosely bound into orbit around Mars. If a propellant temperature of 2000 K is assumed, then low Mars orbit can be attained; while if 3100 K is assumed, then the ballistic NIMF is capable of injecting itself onto a minimum energy transfer orbit to Earth in a direct ascent from the Martian surface

  10. Discussion on the trend of information resource utilization in nuclear power enterprise

    International Nuclear Information System (INIS)

    Cheng Lihong

    2010-01-01

    Content of abstract The use for information resources of nuclear power enterprises will play increasingly vital role in network environment and market competition. Based on the digitization library and archives management conception, Nuclear power enterprise intelligence information service should achieve its function as 'the reference centre of the of administration and decision-making', 'the implement centre of work', 'the museum that witnesses the development and assimilates experience', 'the resource centre for employee's training' for the enterprise combining with the archives center resource by using the technology of digitization and network to deepen the professional edit and research and searches service, which establishes incorporate information management environment for the enterprise. In the process of digitization and informationization management for scientific and technical information construction, enterprise should perform according to its state by stages, ensuring a field carrying out a job according to reality. With the transformation of intelligence information service pattern, an enterprise should pay attention to the ability improvement and the role transformation of the intelligence agent, also to the intellectual property rights during the process and use of information resources. (authors)

  11. Nuclear fuel, with emphasis on its utilization in pressurized water reactor

    International Nuclear Information System (INIS)

    Khazaneh, R.; Roshanzamir, M.

    1997-01-01

    Production processes of nuclear fuel on one hand and using nuclear fuels in reactors, particularly PWR Type reactors on the other hand is investigated. The first chapter reviews the relationship between fuel and reactors; The principals of reactor physics in relation with fuel are described shortly. The second chapter reviews uranium exploration and extraction as well as production of uranium concentrate and uranium dioxides. The third chapter is specified to the different procedures of uranium enrichment. In the fourth chapter, processing of uranium dioxide powder and fuel pellet is described. In the fifth chapter fabrication of fuel rod and fuel assemblies is explained thoroughly. The sixth chapter devoted to the different phenomena which occur ed in fuel structure and can during operational time of reactor; damage to fuel rods and developing theoretical models to describe these phenomena and analysis of fuel structure. The seventh chapter discusses how fuel rods are to be experimented during fabrication, operation and development of technology. The eighth chapter explains different fuels such as uranium compounds and mixed oxide fuel of uranium Gadolinium and uranium plutonium and the process of fabrication of zircaloy. In the tenth chapter, fuel reprocessing is investigated and the difficulties of developing this technology is referred

  12. Approaches for optimizing the utilization of nuclear medical resources in developing countries

    International Nuclear Information System (INIS)

    Adelstein, S.

    1978-10-01

    Contemplation of the use of nuclear medicine technologies in developing countries raises the issue, what purposes they would serve in relation to the major health needs of the region. This investigation was an attempt to assess and to test a methodology for conducting this assessment. Several potential nuclear medicine applications were selected on the basis of their intrinsic promise and in order to evaluate a variety of techniques. These applications were then subjected to a cost-effectiveness analysis, either on their own or in comparison with some competing procedure. To give reality to the study, it was performed in the context of the Indian health scene. The situations examined were the following: Screening blood units for hepatitis B surface antigen prior to transfusion. Costs and benefits of radiorespirometry and conventional culture methods as means to improve case-finding in tuberculosis surveys. Improved tests for diagnosing tuberculous meningitis. Population screening for thyroid diseases. Studies of this type are typically impeded by an insufficiency of key data, they nevertheless can shed some light on the value of potential radionuclide applications

  13. Utilization of uranium cost/benefit study for nuclear powered merchant ships. Special study

    International Nuclear Information System (INIS)

    Smith, E.R.

    1977-05-01

    This study presents a cost/benefit analysis for the utilization of uranium in merchant ships versus the use of uranium for the generation of electricity in central power stations. The study concludes that an alternative naval fuel to oil must be developed for the merchant marine to reduce U.S. dependency upon foreign supplies of a critical fuel. The study further indicates that use of uranium for ship propulsion results in transport of large quantities of needed import/exports while the residual oil saved will generate the same quantity of electricity in a central power station as the uranium used for ship propulsion

  14. Report on progress of researches by common utilization of nuclear facilities, for fiscal 1980

    International Nuclear Information System (INIS)

    1981-01-01

    The common utilization of the facilities in the Japan Atomic Energy Research Institute by universities has been carried out for 20 years, and it contributed very much to the progress of the basic researches on atomic energy and the training of the persons concerned to atomic energy. This report is to be published, summarizing the results of researches carried out actively in 1980. The total number of the subjects in the common utilization of reactors and others was 126, and the total number of visitors during one year was 3356 man-day. 19 cold rooms and 6 hot rooms were leased from the JAERI as the university open laboratory, and Ge(Li) semiconductor detectors, multiple pulse height analyzers, gas chromatography, spectrophotometers, Moessbauer effect measuring equipments, X-ray diffraction equipments and others are installed. A minicomputer was installed in 1978, and preparation is in progress so as to be available as a new correlation measuring equipment. A pure Ge semiconductor detector and a 4000-channel multiple pulse height analyzer were additionally installed in 1980. The state of RI management and radiation control in the open laboratory is reported. The abstracts of the research reports are provided. (Kako, I.)

  15. Decision analysis for the siting of nuclear power plants: the relevance of multiattribute utility theory

    International Nuclear Information System (INIS)

    Keeney, R.L; Nair, K.

    1975-01-01

    The necessity for improved decision making concerning the siting and licensing of major power facilities has been accelerated in the past decade by the increased environmental consciousness of the public and by the energy crisis. These problems are exceedingly complex due to their multiple objective nature, the many interest groups, the long-range time horizons, and the inherent uncertainties of the potential impacts of any decision. Along with the relatively objective economic and engineering concerns, clearly the more subjective factors involving safety, environmental, and social issues are crucial to the problem. Hence, the professional judgments and knowledge of experts in these areas should be utilized in analyses of siting decisions. Likewise, the preferences of the general public, as consumers, the utility companies, as builders and operators of power plant facilities, and environmentalists and the government must be accounted for in analyzing power plant siting and licensing issues. We advocate an approach for formally articulating the experts' judgments and the decision makers' preferences, both of which are clearly subjective, and processing these along with the more objective considerations in a logical manner to acquire the implications for decision making. The appropriateness and application of decision analysis for power plant location decisions is discussed and illustrated. Emphasis is placed on the assessment of the decision maker's preferences and tradeoffs concerning multiple objectives. (U.S.)

  16. Development and utilization of indicators to summarize and represent performance of nuclear power plants

    International Nuclear Information System (INIS)

    Kawaguchi, Hiroshi; Kakubari, Yukihiro; Kikkawa, Shigeru

    1996-01-01

    We have developed eight performance indicators (PIs) that enable quantitative and overall comprehension of operating performance. Among these eight indicators there are 'capability factor' 'incidents and failures' and 'radiation exposure and radioactive wastes', all used to represent the safety and reliability of a nuclear power plant. Results of analysis and evaluation by means of these PIs are distributed to the regulatory agency and other organizations every year, for the benefit of all involved. We have also been examining a technique that may allow synthesis of these PIs into a single, simpler comprehensive indicator that covers all aspects of plant performance. In this report, we present analysis and evaluation of the PIs, the technique to provide a comprehensive performance indicators and actual application. (author)

  17. The engineering of a nuclear thermal landing and ascent vehicle utilizing indigenous Martian propellant

    Science.gov (United States)

    Zubrin, Robert M.

    1990-01-01

    A design study of a novel space transportation concept called NIMF (Nuclear rocket using Indigenous Martian Fuel) is reported. In this concept, Martian CO2 gas, which constitutes 95 percent of the atmosphere, is liquified by simple compression to about 100 psi and remains stable without refrigeration. When heated and exhausted out of a rocket nozzle, a specific impulse of about 264 s can be achieved, sufficient for flights from the surface to highly energetic orbits or from one point on the surface to any other point. The propellant acquisition system can travel with the vehicle, allowing it to refuel itself each time it lands. The concept offers unequalled potential to achieve planetwide mobility, allowing complete global access for the exploration of Mars. By eliminating the necessity of transporting ascent propellant to Mars, the NIMF can also significantly reduce the initial mass in LEO and of a manned Mars mission.

  18. Utilization of red mud for the purification of waste waters from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Luka, Mikelic; Visnja, Orescanin; Stipe, Lulic [Rudjer Boskovic Institute, Lab. for radioecology, Zagreb (Croatia)

    2006-07-01

    Sorption of the radionuclides and heavy metals from low level liquid radioactive waste on the coagulant produced from bauxite waste (red mud and waste base) was presented. Research was conducted on composite annual samples of waste water collected in the Waste Monitor Tank (W.M.T.) from Kro Nuclear Power Plant during each month. Activities of radionuclide in W.M.T. were measured before and after purification using high purity germanium detector. Also, elemental concentrations in W.M.T. before and after purification were measured by source excited energy dispersive X-ray fluorescence (E.D.X.R.F.). It has been showed that activated red mud is excellent purification agent for the removal of radionuclides present in low level liquid radioactive waste. Removal efficiency was 100% for the radionuclides {sup 58}Co and {sup 60}Co 100%, and over 60% for {sup 134}Cs and {sup 137}Cs. (authors)

  19. Utilization of red mud for the purification of waste waters from nuclear power plants

    International Nuclear Information System (INIS)

    Luka, Mikelic; Visnja, Orescanin; Stipe, Lulic

    2006-01-01

    Sorption of the radionuclides and heavy metals from low level liquid radioactive waste on the coagulant produced from bauxite waste (red mud and waste base) was presented. Research was conducted on composite annual samples of waste water collected in the Waste Monitor Tank (W.M.T.) from Kro Nuclear Power Plant during each month. Activities of radionuclide in W.M.T. were measured before and after purification using high purity germanium detector. Also, elemental concentrations in W.M.T. before and after purification were measured by source excited energy dispersive X-ray fluorescence (E.D.X.R.F.). It has been showed that activated red mud is excellent purification agent for the removal of radionuclides present in low level liquid radioactive waste. Removal efficiency was 100% for the radionuclides 58 Co and 60 Co 100%, and over 60% for 134 Cs and 137 Cs. (authors)

  20. Benefits of utilizing CellProfiler as a characterization tool for U–10Mo nuclear fuel

    International Nuclear Information System (INIS)

    Collette, R.; Douglas, J.; Patterson, L.; Bahun, G.; King, J.; Keiser, D.; Schulthess, J.

    2015-01-01

    Automated image processing techniques have the potential to aid in the performance evaluation of nuclear fuels by eliminating judgment calls that may vary from person-to-person or sample-to-sample. Analysis of in-core fuel performance is required for design and safety evaluations related to almost every aspect of the nuclear fuel cycle. This study presents a methodology for assessing the quality of uranium–molybdenum fuel images and describes image analysis routines designed for the characterization of several important microstructural properties. The analyses are performed in CellProfiler, an open-source program designed to enable biologists without training in computer vision or programming to automatically extract cellular measurements from large image sets. The quality metric scores an image based on three parameters: the illumination gradient across the image, the overall focus of the image, and the fraction of the image that contains scratches. The metric presents the user with the ability to ‘pass’ or ‘fail’ an image based on a reproducible quality score. Passable images may then be characterized through a separate CellProfiler pipeline, which enlists a variety of common image analysis techniques. The results demonstrate the ability to reliably pass or fail images based on the illumination, focus, and scratch fraction of the image, followed by automatic extraction of morphological data with respect to fission gas voids, interaction layers, and grain boundaries. - Graphical abstract: Display Omitted - Highlights: • A technique is developed to score U–10Mo FIB-SEM image quality using CellProfiler. • The pass/fail metric is based on image illumination, focus, and area scratched. • Automated image analysis is performed in pipeline fashion to characterize images. • Fission gas void, interaction layer, and grain boundary coverage data is extracted. • Preliminary characterization results demonstrate consistency of the algorithm

  1. Benefits of utilizing CellProfiler as a characterization tool for U–10Mo nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Collette, R.; Douglas, J.; Patterson, L.; Bahun, G. [Nuclear Science and Engineering Program, Colorado School of Mines, 1500 Illinois St, Golden, CO 80401 (United States); King, J., E-mail: kingjc@mines.edu [Nuclear Science and Engineering Program, Colorado School of Mines, 1500 Illinois St, Golden, CO 80401 (United States); Keiser, D.; Schulthess, J. [Nuclear Fuels and Materials Division, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188 (United States)

    2015-07-15

    Automated image processing techniques have the potential to aid in the performance evaluation of nuclear fuels by eliminating judgment calls that may vary from person-to-person or sample-to-sample. Analysis of in-core fuel performance is required for design and safety evaluations related to almost every aspect of the nuclear fuel cycle. This study presents a methodology for assessing the quality of uranium–molybdenum fuel images and describes image analysis routines designed for the characterization of several important microstructural properties. The analyses are performed in CellProfiler, an open-source program designed to enable biologists without training in computer vision or programming to automatically extract cellular measurements from large image sets. The quality metric scores an image based on three parameters: the illumination gradient across the image, the overall focus of the image, and the fraction of the image that contains scratches. The metric presents the user with the ability to ‘pass’ or ‘fail’ an image based on a reproducible quality score. Passable images may then be characterized through a separate CellProfiler pipeline, which enlists a variety of common image analysis techniques. The results demonstrate the ability to reliably pass or fail images based on the illumination, focus, and scratch fraction of the image, followed by automatic extraction of morphological data with respect to fission gas voids, interaction layers, and grain boundaries. - Graphical abstract: Display Omitted - Highlights: • A technique is developed to score U–10Mo FIB-SEM image quality using CellProfiler. • The pass/fail metric is based on image illumination, focus, and area scratched. • Automated image analysis is performed in pipeline fashion to characterize images. • Fission gas void, interaction layer, and grain boundary coverage data is extracted. • Preliminary characterization results demonstrate consistency of the algorithm.

  2. Shift systems in nuclear power plants - aspects for planning, shift systems, utility practice

    International Nuclear Information System (INIS)

    Grauf, E.

    1986-01-01

    This lecture contains the most important aspects of shift structure and shift organisation. The criteria for shift planning involving essential tasks, duties, laws and regulations, medical aspects, social aspects, will be presented. In the Federal Republic of Germany some basic models were established, which will be shown and explained with special reference to the number of teams, size of shift crews and absence regulations. Moreover, the lecture will deal with rotation systems and provisions for the transfer of shift responsibilities. By example of a utility plant commissioning time scale (1300 MW PWR) the practice of shift installations will be shown as well as the most important points of education and training. Within this compass the criteria and requirements for training and education of operational personnel in the Federal Republic of Germany will also be touched. (orig.)

  3. Recovery and utilization of valuable metals from spent nuclear fuel. 3: Mutual separation of valuable metals

    International Nuclear Information System (INIS)

    Kirishima, K.; Shibayama, H.; Nakahira, H.; Shimauchi, H.; Myochin, M.; Wada, Y.; Kawase, K.; Kishimoto, Y.

    1993-01-01

    In the project ''Recovery and Utilization of Valuable Metals from Spent Fuel,'' mutual separation process of valuable metals recovered from spent fuel has been studied by using the simulated solution contained Pb, Ru, Rh, Pd and Mo. Pd was separated successfully by DHS (di-hexyl sulfide) solvent extraction method, while Pb was recovered selectively from the raffinate by neutralization precipitation of other elements. On the other hand, Rh was roughly separated by washing the precipitate with alkaline solution, so that Rh was refined by chelate resin CS-346. Outline of the mutual separation process flow sheet has been established of the combination of these techniques. The experimental results and the process flow sheet of mutual separation of valuable metals are presented in this paper

  4. Spent fuel storage requirements for nuclear utilities and OCRWM [Office of Civilian Radioactive Waste Management

    International Nuclear Information System (INIS)

    Wood, T.W.

    1990-03-01

    Projected spent fuel generation at US power reactors exceeds estimated aggregate pool storage capacity by approximately 30,000 metric tons of uranium (MTU). Based on the current repository schedule, little of the spent fuel inventory will be disposed of prior to shutdown of existing reactors, and a large additional capacity for surface storage of spent fuel will be required, either at reactors or at a centralized DOE storage site. Allocation of this storage requirement across the utility-DOE interface, and the resulting implications for reactor sites and the performance of the federal waste management system, were studied during the DOE MRS System Study and again subsequent to the reassessment of the repository schedule. Spent fuel logistics and cost results from these analyses will be used in definition of spent fuel storage capacity requirements for the federal system. 9 refs., 8 figs., 1 tab

  5. Direct utilization of information from nuclear data files in Monte Carlo simulation of neutron and photon transport

    International Nuclear Information System (INIS)

    Androsenko, P.; Joloudov, D.; Kompaniyets, A.

    2001-01-01

    Questions, related to Monte-Carlo method for solution of neutron and photon transport equation, are discussed in the work concerned. Problems dealing with direct utilization of information from evaluated nuclear data files in run-time calculations are considered. ENDF-6 format libraries have been used for calculations. Approaches provided by the rules of ENDF-6 files 2, 3-6, 12-15, 23, 27 and algorithms for reconstruction of resolved and unresolved resonance region cross sections under preset energy are described. The comparison results of calculations made by NJOY and GRUCON programs and computed cross sections data are represented. Test computation data of neutron leakage spectra for spherical benchmark-experiments are also represented. (authors)

  6. Out-of-core nuclear fuel cycle optimization utilizing an engineering workstation

    International Nuclear Information System (INIS)

    Turinsky, P.J.; Comes, S.A.

    1986-01-01

    Within the past several years, rapid advances in computer technology have resulted in substantial increases in their performance. The net effect is that problems that could previously only be executed on mainframe computers can now be executed on micro- and minicomputers. The authors are interested in developing an engineering workstation for nuclear fuel management applications. An engineering workstation is defined as a microcomputer with enhanced graphics and communication capabilities. Current fuel management applications range from using workstations as front-end/back-end processors for mainframe computers to completing fuel management scoping calculations. More recently, interest in using workstations for final in-core design calculations has appeared. The authors have used the VAX 11/750 minicomputer, which is not truly an engineering workstation but has comparable performance, to complete both in-core and out-of-core fuel management scoping studies. In this paper, the authors concentrate on our out-of-core research. While much previous work in this area has dealt with decisions concerned with equilibrium cycles, the current project addresses the more realistic situation of nonequilibrium cycles

  7. Utilization the nuclear techniques use to estimate the water erosion in tobacco plantations in Cuba

    International Nuclear Information System (INIS)

    Gil, Reinaldo H.; Peralta, José L.; Carrazana, Jorge; Fleitas, Gema; Aguilar, Yulaidis; Rivero, Mario; Morejón, Yilian M.; Oliveira, Jorge

    2015-01-01

    Soil erosion is a relevant factor in land degradation, causing several negative impacts to different levels in the environment, agriculture, etc. The tobacco plantations in the western part of the country have been negatively affected by the water erosion due to natural and human factors. For the implementation of a strategy for sustainable land management a key element is to quantify the soil losses in order to establish policies for soil conservation. The nuclear techniques have advantages in comparison with the traditional methods to assess soil erosion and have been applied in different agricultural settings worldwide. The tobacco cultivation in Pinar del Río is placed on soils with high erosion levels, therefore is important to apply techniques which support the soil erosion rate quantification. This work shows the use of "1"3"7Cs technique to characterize the soil erosion status in two sectors in a farm with tobacco plantations located in the south-western plain of Pinar del Rio province. The sampling strategy included the evaluation of selected transects in the slope direction for the studied site. The soil samples were collected in order to incorporate the whole "1"3"7Cs profile. Different conversion models were applied and the Mass Balance Model II provided the more representative results, estimating the soil erosion rate from –18,28 to 8,15 t ha"-"1año"-"1. (author)

  8. Re-utilization of concrete from decommissioned nuclear facilities by re-clinkering

    International Nuclear Information System (INIS)

    Costes, J.R.

    1998-01-01

    Usually concrete is reused as aggregates. To maximize reusing by producing a new concrete, separation of its fundamental components (aggregates, sand, cement) is required. But can already hydrated cement be re-clinkered and become new good cement again? This paper shows how specimen of pure cement paste of ordinary Portland cement was hydrated then crushed and reclinkerised. Chemical and, X ray diffraction analysis, electronic microscope coupled with X fluorescence observations, demonstrate that very few differences occurs in the cement paste before and after re-clinkering; mechanical properties of the reactivated powder are very satisfactory, even exceeding the strength of the original pure cement paste. As this process involves heating up to 1450 deg C, some of the contamination (caesium, ruthenium) may also be eliminated by volatilization and recovery on filters. This process could be very promising to complete recycle large quantities of low level contaminated concrete inside the nuclear industry as alternative to storage in specific and expensive dump, as it is now the case for steel materials. (authors)

  9. Utilization of the noble gases in studies of underground nuclear detonations

    International Nuclear Information System (INIS)

    Smith, C.F.

    1973-01-01

    The Livermore Gas Diagnostics Program employs a number of rare gas isotopes, both stable and radioactive, in its investigations of the phenomenology of underground nuclear detonations. Radioactive gases in a sample are radiochemically purified by elution chromatography, and the separated gases are radioassayed by gamma-ray spectrometry and by internal or thin-window beta proportional counting. Concentrations of the stable gases are determined by mass-spectrometry, following chemical removal of the reactive gases in the sample. The most general application of the noble gases is as device fraction indicators to provide a basis for estimating totals of chimney-gas components. All of the stable rare gases, except argon, have been used as tracers, as have xenon-127 and krypton-85. Argon-37 and krypton-85 have proven to be of particular value in the absence of a good tracer material as reference species for studies of chimney-gas chemistry. The rate of mixing of chimney gases, and the degree to which the sampled gas truly represents the underground gas mixture, can be studied with the aid of the fission-product gases. Radon-222 and helium are released to the cavity from the surrounding rock, and are, therefore, useful in studies of the interaction of the detonation with the surrounding medium

  10. An Overview of Strategic Utilization Plan for the Moroccan Nuclear Research Reactor over the Period of 2010–2015

    International Nuclear Information System (INIS)

    Jibre, A.; Boufraqech, A.

    2013-01-01

    The National Centre for Nuclear Energy, Science and Technology (CNESTEN), a Moroccan state-owned company, is setting up a strategic utilization plan for its recently commissioned and licensed nuclear research reactor, Triga Mark II, 2 MW, over the period of 2010–2015. This strategic plan is aiming to efficiently and effectively meet existing and potential needs: research and development, education and training, and generally all related products and services, both at national and regional level, within a sustainable framework. For that purpose, CNESTEN’s vision is to develop and strengthen its position in the market place by fully integrating both operational and logistical issues in being strategically led, market oriented, competitively focused, operationally efficient, revenue generating applications emphasized, and human resources driven. In terms of existing and potential services and products to be delivered from the research reactor, CNESTEN is more focusing on education and training, for which an international training centre is under development; radioisotopes production, for both medical and industrial uses for which CNESTEN has a leading national position; analytical techniques such as NAA and PGNAA; neutron beam techniques such as neutron imaging and neutron diffraction; and irradiation services for NTD. (author)

  11. IEA-R1 Nuclear Research Reactor: 58 Years of Operating Experience and Utilization for Research, Teaching and Radioisotopes Production

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas, Jose Patricio Nahuel; Filho, Tufic Madi; Saxena, Rajendra; Filho, Walter Ricci [Nuclear and Energy Research Institute, IPEN-CNEN/SP, Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP, Av. Prof. Lineu Prestes 2242 Cid Universitaria CEP: 05508-000- Sao Paulo-SP (Brazil)

    2015-07-01

    IEA-R1 research reactor at the Instituto de Pesquisas Energeticas e Nucleares (Nuclear and Energy Research Institute) IPEN, Sao Paulo, Brazil is the largest power research reactor in Brazil, with a maximum power rating of 5 MWth. It is being used for basic and applied research in the nuclear and neutron related sciences, for the production of radioisotopes for medical and industrial applications, and for providing services of neutron activation analysis, real time neutron radiography, and neutron transmutation doping of silicon. IEA-R1 is a swimming pool reactor, with light water as the coolant and moderator, and graphite and beryllium as reflectors. The reactor was commissioned on September 16, 1957 and achieved its first criticality. It is currently operating at 4.5 MWth with a 60-hour cycle per week. In the early sixties, IPEN produced {sup 131}I, {sup 32}P, {sup 198}Au, {sup 24}Na, {sup 35}S, {sup 51}Cr and labeled compounds for medical use. During the past several years, a concerted effort has been made in order to upgrade the reactor power to 5 MWth through refurbishment and modernization programs. One of the reasons for this decision was to produce {sup 99}Mo at IPEN. The reactor cycle will be gradually increased to 120 hours per week continuous operation. It is anticipated that these programs will assure the safe and sustainable operation of the IEA-R1 reactor for several more years, to produce important primary radioisotopes {sup 99}Mo, {sup 125}I, {sup 131}I, {sup 153}Sm and {sup 192}Ir. Currently, all aspects of dealing with fuel element fabrication, fuel transportation, isotope processing, and spent fuel storage are handled by IPEN at the site. The reactor modernization program is slated for completion by 2015. This paper describes 58 years of operating experience and utilization of the IEA-R1 research reactor for research, teaching and radioisotopes production. (authors)

  12. A preliminary assessment of the radiological implications of commercial utilization of natural gas from a nuclearly stimulated well

    Energy Technology Data Exchange (ETDEWEB)

    Jacobs, D G; Struxness, E G [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States); Bowman, C R [El Paso Natural Gas Company, El Paso, TX (United States)

    1970-05-01

    Widespread utilization of nuclear explosives, in conjunction with the natural gas industry, can result in radiation exposure of sizable population groups. It is prudent to make realistic assessments of such potential radiation exposures before they occur and, unless the expected exposures are clearly insignificant, to consider these exposures in evaluating the net benefit of this particular use of nuclear energy. All pertinent facts relating to such assessments should be made public and presented in such a way that those who are to assume the risks, if any, can make a reasonable judgment as to whether the risks are acceptable. Radioactivity in natural gas from the Gasbuggy cavity has been analyzed prior to and during flaring operations. None of this gas has entered the collection and distribution system, but a theoretical analysis has been made of the hypothetical impact on members of the public that would have occurred if the gas had been introduced into the commercial stream. Dose equivalents have been estimated for both workers and consumers. In this analysis, Gasbuggy gas has been traced through a real gas-collection system and processing plant, as represented by the present situation existing in the San Juan Production Division, El Paso Natural Gas Company. In addition, a number of considerations are presented which would apply to radiation exposure in metropolitan areas. Results of this analysis for the Gasbuggy well indicate hypothetical dose equivalents to various population groups to be well within the annual dose limits suggested by the International Commission on Radiological Protection. Projection to a steady-state situation involving extensive natural gas production from many producing wells also resulted in hypothetical dose equivalents within the annual dose limits. Simple extrapolation of the results from this analysis to potential exposures resulting from nuclear stimulation of other gas reservoirs cannot be made on a direct basis, but this method

  13. A preliminary assessment of the radiological implications of commercial utilization of natural gas from a nuclearly stimulated well

    International Nuclear Information System (INIS)

    Jacobs, D.G.; Struxness, E.G.; Bowman, C.R.

    1970-01-01

    Widespread utilization of nuclear explosives, in conjunction with the natural gas industry, can result in radiation exposure of sizable population groups. It is prudent to make realistic assessments of such potential radiation exposures before they occur and, unless the expected exposures are clearly insignificant, to consider these exposures in evaluating the net benefit of this particular use of nuclear energy. All pertinent facts relating to such assessments should be made public and presented in such a way that those who are to assume the risks, if any, can make a reasonable judgment as to whether the risks are acceptable. Radioactivity in natural gas from the Gasbuggy cavity has been analyzed prior to and during flaring operations. None of this gas has entered the collection and distribution system, but a theoretical analysis has been made of the hypothetical impact on members of the public that would have occurred if the gas had been introduced into the commercial stream. Dose equivalents have been estimated for both workers and consumers. In this analysis, Gasbuggy gas has been traced through a real gas-collection system and processing plant, as represented by the present situation existing in the San Juan Production Division, El Paso Natural Gas Company. In addition, a number of considerations are presented which would apply to radiation exposure in metropolitan areas. Results of this analysis for the Gasbuggy well indicate hypothetical dose equivalents to various population groups to be well within the annual dose limits suggested by the International Commission on Radiological Protection. Projection to a steady-state situation involving extensive natural gas production from many producing wells also resulted in hypothetical dose equivalents within the annual dose limits. Simple extrapolation of the results from this analysis to potential exposures resulting from nuclear stimulation of other gas reservoirs cannot be made on a direct basis, but this method

  14. Information Exchange among COG Member Stations, Utility/AECL Design and External Nuclear Organizations

    International Nuclear Information System (INIS)

    Turner, Dave

    1998-01-01

    The paper presents the COG Information Exchange Program the mandate of which reads: 'To promote the safety reliability and excellence of CANDU plants worldwide by facilitating the sharing of operating experience amongst the members of COG'. To fulfill its mandate the COG operates Information Exchange Program which: 1. Provides a user-friendly facility, COGNET, for staff of COG member organizations to communicate with each other and with external stations, utilities and organizations on topics applicable to CANDU operation, safety, maintenance, design and performance; 2. Offers one-stop shopping for information applicable to the design, operation, maintenance, safety and performance of CANDU's; 3. Reports and compares the performance of all CANDU stations; 4. Organizes opportunities for individuals involved with the operation of CANDU's to meet with their peers and with CANDU industry experts to share operating experience; 5. Facilitates the identification of generic CANDU problems which leads to the addressing of these problems by others through co-operative projects, designer feedback and R and D programs. The paper has the following content: 1. COGNET; 1.1. COGNET Message Forums; 1.2. COGNET Operations Forums; 1.3. COGNET Private Messages; 2. Report Databases and Library; 2.1. REPEX (Technical Reports); 2.2. PCN (CANDU Plant Modifications); 2.3. SEREX (CANDU Station Events); 2.4. INPO (International Events); 3. CANDU Performance; 3.1. COG NEWSLETTERS; 3.2. Performance Indicators; 4. Workshops; 4.1. COG Workshops

  15. Utilization of neutrons in nuclear data measurements and bulk sample analysis

    International Nuclear Information System (INIS)

    Jonah, S. A.

    1995-01-01

    Experimental investigations were carried out with neutrons in the fields of neutron data measurements and bulk sample analysis based on the interactions of neutron interactions required in the investigations together with some salient features of the sources employed are enumerated. Excitation cross section curves and isomeric cross section ratio of 58 Ni(n,p) 58 Co m , g reaction over the neutron energy range of between 5 and 15 MeV were determined using the activation analysis technique in combination with high-resolution gamma spectroscopy. Characteristics of the incident neutrons produced via the D-T reaction of a neutron generator and D-D reaction of a cyclotron were determined experimentally to account for the contributing effects of background neutrons especially in the 5-13 MeV neutron energy range where existing data are scanty and rather discrepant. The measured data agree well with calculated data using nuclear models but deviate significantly from the recommended data based on existing literature data. The measured δ act and δ m /δ g data made it possible to determine the cross section curve for 58 Ni(n,p) 58 Co m reaction. Furthermore the flux density distributions of thermal and primary fast neutrons in different configurations of bulk samples consisting of water, graphite and coal together with the attenuation characteristics were determined by the activation analysis and pulse height response spectrometry techniques. From the results obtained, an experimental geometry has been proposed for on-line elemental analysis of coal and other minerals. Similarly the total hydrogen content and 0+C/H atomic ratio in household and motor oils as well as crude oil samples of different origins were measured by an improved experimental arrangement based on the thermal neutron reflection technique. A detection limit of 0.12 w % was obtained for hydrogen indicating the possible adaptation of this technique for quality control of petroleum products

  16. Single event upset mitigation techniques for FPGAs utilized in nuclear power plant digital instrumentation and control

    International Nuclear Information System (INIS)

    Wang Xin; Holbert, Keith E.; Clark, Lawrence T.

    2011-01-01

    Highlights: → Triple modular redundancy (TMR) implementation is the best solution for digital I and C. → Maximal probability of two simultaneous errors with TMR maximum partition is 4.44%. → Dual modular redundancy minimum logic partitioning design is an additional option. - Abstract: Field programmable gate arrays (FPGAs) are integrated circuits being increasingly used for digital instrumentation and control (I and C) in nuclear power plants (NPPs) because of low cost, re-configurability and low design turn-around time. However, to ensure reliability, proper design techniques must be employed since the memory and logic in FPGAs are susceptible to single event upsets (SEUs). Triple modular redundancy (TMR) has become a common SEU mitigation design technique because of its straightforward implementation and reliable results. Partitioned TMR approaches are introduced in this paper, and formulae derived indicate that the maximum probability of two simultaneous errors [P E ] max is inversely proportional to the number of logic partitions in a TMR design, when each redundant logic block in every logic partition has the same number of sensitive nodes. However, the maximum logic partitioning design cannot completely eliminate the possibility of two simultaneous upsets. For the example test circuit it is found that [P E ] max is reduced dramatically from 66.67% for minimum logic partitioning to 4.44% for maximum logic partitioning. Because TMR introduces significant overhead due to its full hardware redundancy, a dual modular redundancy approach is also examined for application to less demanding situations. By comparative analysis this study reaches the conclusion that the maximum logic partitioning TMR implementation is the best solution for digital I and C applications in NPPs where obtaining robustness is of the highest importance, despite its higher area overhead.

  17. The utilization of performance evaluation instruments by technical trainers to evaluate maintenance personnel in the nuclear power industry in the United States

    International Nuclear Information System (INIS)

    Hornberger, C.K.

    1993-01-01

    The purpose of this study was to document the utilization of performance evaluation instruments by technical trainers in the evaluation of maintenance personnel in US nuclear power plants. Performance evaluation of maintenance personnel has been identified by nuclear utilities and the Nuclear Regulatory Commission as the only acceptable method of determining worker competence. The NRC requires performance evaluation to be conducted to performance standards, but it does not specify the standards or the method to be utilized. Each plant is free to establish its own standards and methods of evaluation. This was a descriptive study utilizing descriptive statistics for the analysis of the data. The subjects included 655 maintenance trainers in 72 US nuclear plants. Conclusions of the study include: (1) Technical trainers are in compliance with NRC regulations. (2) Evaluation materials developed by the Institute of Nuclear Power Operations are used by technical trainers in every one of the 62 plants that responded. (3) In-plant or self-developed Performance Evaluation Instruments are utilized by 419 or 95.2% of the technical trainers. (4) Technical trainers incorporate nine common components into their Performance Evaluation Instruments. (5) Technical trainers evaluate maintenance processes and the product produced by workers when following procedures and specifications are critical and when safety hazards are involved. (6) Technical trainers believe that utilizing Performance Evaluation Instruments makes their job easier by providing documentation about the quality and standards of maintenance skills. (7) Technical trainers believe that maintenance workers benefit when their skills are assessed through the use of Performance Evaluation Instruments

  18. Practice and prospects of creation of equipment for reprocessing and utilization of contaminated metal wastes of plants of nuclear industry in Russia

    International Nuclear Information System (INIS)

    Popov, G.P.

    2005-01-01

    Program of reprocessing and utilization of metallic radioactive wastes exists in Russia. In the framework of this program in nuclear industry it is accumulated forty years experience on taking-off-service, disassembly, decontamination and reprocessing of technological facilities. Some technical characteristics of the units used for these operations are represented [ru

  19. The new framework for resolving the energy problem and its application to the utilization of nuclear technology

    International Nuclear Information System (INIS)

    Kurata, Kenji

    2002-01-01

    Until recently, the energy problem in Japan had been the problem of how enough energy could be supplied to various sectors in society under Japan's conditions of only a few energy resources existing within its territory. However, recently new environmental and social conditions are arising. These new conditions strongly affect not only concrete measures for solving the energy problem but also the characteristics of the energy problem itself. Nowadays, it seems to be impossible to resolve the energy problem without taking these conditions into consideration. For this reason, a new framework, which enables various social values to be reflected in concrete measures, is urgently needed to resolve the energy problem. This thesis uses the ISO14001 framework to consider a possible solution over the energy problem. In the first part of this thesis, an examination shows that the ISO14001 framework should be generalized beyond the original objective of dealing with environmental problems to accommodate any kind of problems caused by newly arising social values. This generalized framework is defined as a 'Social measure' and expected to enhance the resolution of the problem in socially appropriate manner. In the second part, this paper uses the idea of the Social measure to consider a possible solution to recover public trust on the utilization of nuclear technology, which is regarded as a typical energy problem under the social condition. (author)

  20. EMI environment EMC considerations concerning equipment upgrades at a nuclear utility power generating station a case history

    International Nuclear Information System (INIS)

    Metcalf, M.J.

    1993-01-01

    As equipment is upgraded during scheduled power outages in nuclear power generating stations, more and more utilities will be faced with the problem of dealing with Electromagnetic Compatibility (EMC) issues that have evolved with the trend of manufacturers designing equipment based around state-of-the-art high technology logic devices. This paper lists Commonwealth Edison Company (CECO) equipment that was scrutinized by National Technical Systems (NTS) for its EMI impact. The test requirements and test procedures for assessing EMI and EMC are outlined. Although on-site mapping data was gathered to assist CECO for the upgrade described here of the Auxiliary Electric Equipment Room of a Westinghouse Eagle 21 Reactor Protection System at the Zion Unit No.1 Station, blanket mapping of every location for every upgrade is a short term, expensive solution to the EMI problem. It is concluded that the primary problem of lack of system and component level EMI specifications must be addressed by a governing body. 7 refs., 2 figs

  1. Public acceptance of the utilization of nuclear technology. Necessity of using the system which is similar to that of the ISO14001

    International Nuclear Information System (INIS)

    Kurata, Kenji; Kanda, Keiji

    2001-01-01

    Safety itself is a key factor in enhancing public acceptance of the utilization of nuclear technology. At the same time, it is indispensable for businesses using nuclear technology to foster public trust by being regarded as 'companies which are making serious efforts to attain higher level of safety'. However, recent nuclear accidents related to the MONJU plant and JCO have seriously hampered this trust. Based on the above understanding, this paper uses the ISO14001 framework to consider a possible solution to recover public trust. An examination of the ISO14001 shows that it is seen as a framework to prove to the outside world that the party in question is reliable in terms of behaving in an environmentally sound manner. Accordingly, their must be a possibility for businesses using a nuclear technology to be able to use the ideas of the framework in terms of safety instead of the environment. (author)

  2. Study on a program for support of women nuclear experts exchange and mutual utilization between WANO Korea and WANO Global

    International Nuclear Information System (INIS)

    Lee, Haecho; No, Inyoung; Min, Byungju

    2010-12-01

    - Nuclear energy, unlike other international human and material essential to mutual understanding, exchange of information and technology-intensive industries as required by an active technical cooperation and information exchange between countries is very important - WiN-Global Women's Domestic Nuclear specialists and professionals between countries belonging to the network for women through nuclear technology and nuclear power expansion opportunities to exchange information to secure a variety of communication

  3. The utility industry's perspective on OCRWM's plans for developing the system for transporting spent fuel under the Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    Brodnick, D.A.

    1988-01-01

    The electric utility industry has a vital interest in the transport program to be developed by the Department of Energy's Office of Civilian Radioactive Waste Management under the Nuclear Waste Policy Act. The industry's interest stems in part from the fact that the DOE's transportation program is financed by the Nuclear Waste Fund which is made up of ratepayer funds. However, the industry is also vitally interested in the DOE's transportation program because it could impact the ongoing transportation operations of all nuclear utilities, and, perhaps most importantly, without the utility industry's input, DOE is not able to develop an optimal transportation program. The NWPA contemplates that the DOE conducts its transportation program in accordance with the existing federal and state regulatory structure. DOE has significant discretion, however, in creating and implementing the business, operational and institutional aspects of its NWPA transportation program. The utility industry intends to ensure that the DOE meets the challenge to develop a safe, efficient and economically sound program to transport spent fuel and high-level waste to the appropriate federal facilities

  4. Utilization of small-angle neutron scattering to decide the maximum loading of nuclear waste in cement matrix

    International Nuclear Information System (INIS)

    Das, Avik; Mazumder, S.; Sen, D.; Yalmali, V.; Shah, J.G.

    2014-01-01

    Nuclear power plants generate many kinds of hazardous nuclear waste which are needed to be disposed in an eco-friendly manner. Many different waste incarceration techniques have been adapted for managing the nuclear waste of different category of radioactivity. Immobilisation of low and intermediate level radioactive wastes in cement matrix is one of the widely used and cost-effective techniques in waste management. However, loading of nuclear waste in cement matrix can alter the mesoscopic structure of the hydrated cement and hence, it is very important to set the maximum limit of waste loading in cement for providing proper physical isolation to the nuclear waste

  5. Utility of magnetic resonance imaging and nuclear magnetic resonance-based metabolomics for quantification of inflammatory lung injury

    Science.gov (United States)

    Serkova, Natalie J.; Van Rheen, Zachary; Tobias, Meghan; Pitzer, Joshua E.; Wilkinson, J. Erby; Stringer, Kathleen A.

    2008-01-01

    Magnetic resonance imaging (MRI) and metabolic nuclear magnetic resonance (NMR) spectroscopy are clinically available but have had little application in the quantification of experimental lung injury. There is a growing and unfulfilled need for predictive animal models that can improve our understanding of disease pathogenesis and therapeutic intervention. Integration of MRI and NMR could extend the application of experimental data into the clinical setting. This study investigated the ability of MRI and metabolic NMR to detect and quantify inflammation-mediated lung injury. Pulmonary inflammation was induced in male B6C3F1 mice by intratracheal administration of IL-1β and TNF-α under isoflurane anesthesia. Mice underwent MRI at 2, 4, 6, and 24 h after dosing. At 6 and 24 h lungs were harvested for metabolic NMR analysis. Data acquired from IL-1β+TNF-α-treated animals were compared with saline-treated control mice. The hyperintense-to-total lung volume (HTLV) ratio derived from MRI was higher in IL-1β+TNF-α-treated mice compared with control at 2, 4, and 6 h but returned to control levels by 24 h. The ability of MRI to detect pulmonary inflammation was confirmed by the association between HTLV ratio and histological and pathological end points. Principal component analysis of NMR-detectable metabolites also showed a temporal pattern for which energy metabolism-based biomarkers were identified. These data demonstrate that both MRI and metabolic NMR have utility in the detection and quantification of inflammation-mediated lung injury. Integration of these clinically available techniques into experimental models of lung injury could improve the translation of basic science knowledge and information to the clinic. PMID:18441091

  6. Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants: Criteria for utility offsite planning and preparedness: Final report

    International Nuclear Information System (INIS)

    Podolak, E.M. Jr.; Sanders, M.E.; Wingert, V.L.; Donovan, R.W.

    1988-09-01

    The Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) have added a supplement to NUREG-0654/FEMA-REP-1, Rev. 1 that provides guidance for the development, review, and evaluation of utility offsite radiological emergency response planning and preparedness for those situations in which state and/or local governments decline to participate in emergency planning. While this guidance primarily applies to plants that do not have full-power operating licenses, it does have relevance to operating nuclear power plants

  7. Status and development of nuclear energy utilization in the Federal Republic of Germany - as of May 1993

    International Nuclear Information System (INIS)

    Philippczyk, F.; Ziegenhagen, J.

    1993-07-01

    The report states the essential data of all nuclear power plants, the facilities of the nuclear fuel cycle and the storage of radioactive wastes. In 1992, 20 nuclear power plants were in operation. With 158.840 GWh altogether they provided 34% of the total gross electricity production. The report summarizes the essential operational results of the nuclear power plants as well as the use of mixed oxide fuel elements (MOX). A short description of the present state of the nuclear power plants that have been shut down or decommissioned and of the stopped programmes is given. Data on purpose and capacity of facilities of the nuclear fuel cycle and of radioactive waste storage are given. Furthermore, the licensing history and the present state of operation and licensing are represented. Three projects with regard to disposal of radioactive wastes are presented according to their present state. To give a survey, the data are summarized in tabular form in the report annexes. (orig.) [de

  8. Preliminary Thermohydraulic Analysis of a New Moderated Reactor Utilizing an LEU-Fuel for Space Nuclear Thermal Propulsion

    International Nuclear Information System (INIS)

    Nam, Seung Hyun; Choi, Jae Young; Venneria, Paolo F.; Jeong, Yong Hoon; Chang, Soon Heung

    2015-01-01

    The Korea Advanced NUclear Thermal Engine Rocket utilizing an LEU fuel (KANUTER-LEU) is a non-proliferative and comparably efficient NTR engine with relatively low thrust levels of 40 - 50 kN for in-space transportation. The small modular engine can expand mission versatility, when flexibly used in a clustered engine arrangement, so that it can perform various scale missions from low-thrust robotic science missions to high-thrust manned missions. In addition, the clustered engine system can enhance engine redundancy and ensuing crew safety as well as the thrust. The propulsion system is an energy conversion system to transform the thermal energy of the reactor into the kinetic energy of the propellant to produce the powers for thrust, propellant feeding and electricity. It is mainly made up of a propellant Feeding System (PFS) comprising a Turbo-Pump Assembly (TPA), a Regenerative Nozzle Assembly (RNA), etc. For this core design study, an expander cycle is assumed to be the propulsion system. The EGS converts the thermal energy of the EHTGR in the idle operation (only 350 kW th power) to electric power during the electric power mode. This paper presents a preliminary thermohydraulic design analysis to explore the design space for the new reactor and to estimate the referential engine performance. The new non-proliferative NTR engine concept, KANUTER-LEU, is under designing to surmount the nuclear proliferation obstacles on allR and Dactivities and eventual commercialization for future generations. To efficiently implement a heavy LEU fuel for the NTR engine, its reactor design innovatively possesses the key characteristics of the high U density fuel with high heating and H 2 corrosion resistances, the thermal neutron spectrum core and also minimizing non-fission neutron loss, and the compact reactor design with protectively cooling capability. To investigate feasible design space for the moderated EHTGR-LEU and resultant engine performance, the preliminary design

  9. Preliminary Thermohydraulic Analysis of a New Moderated Reactor Utilizing an LEU-Fuel for Space Nuclear Thermal Propulsion

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Seung Hyun; Choi, Jae Young; Venneria, Paolo F.; Jeong, Yong Hoon; Chang, Soon Heung [KAIST, Daejeon (Korea, Republic of)

    2015-10-15

    The Korea Advanced NUclear Thermal Engine Rocket utilizing an LEU fuel (KANUTER-LEU) is a non-proliferative and comparably efficient NTR engine with relatively low thrust levels of 40 - 50 kN for in-space transportation. The small modular engine can expand mission versatility, when flexibly used in a clustered engine arrangement, so that it can perform various scale missions from low-thrust robotic science missions to high-thrust manned missions. In addition, the clustered engine system can enhance engine redundancy and ensuing crew safety as well as the thrust. The propulsion system is an energy conversion system to transform the thermal energy of the reactor into the kinetic energy of the propellant to produce the powers for thrust, propellant feeding and electricity. It is mainly made up of a propellant Feeding System (PFS) comprising a Turbo-Pump Assembly (TPA), a Regenerative Nozzle Assembly (RNA), etc. For this core design study, an expander cycle is assumed to be the propulsion system. The EGS converts the thermal energy of the EHTGR in the idle operation (only 350 kW{sub th} power) to electric power during the electric power mode. This paper presents a preliminary thermohydraulic design analysis to explore the design space for the new reactor and to estimate the referential engine performance. The new non-proliferative NTR engine concept, KANUTER-LEU, is under designing to surmount the nuclear proliferation obstacles on allR and Dactivities and eventual commercialization for future generations. To efficiently implement a heavy LEU fuel for the NTR engine, its reactor design innovatively possesses the key characteristics of the high U density fuel with high heating and H{sub 2} corrosion resistances, the thermal neutron spectrum core and also minimizing non-fission neutron loss, and the compact reactor design with protectively cooling capability. To investigate feasible design space for the moderated EHTGR-LEU and resultant engine performance, the

  10. Utilization of the Differential Die-Away Self-Interrogation Technique for Characterization and Verification of Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Trahan, Alexis Chanel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-01-27

    New nondestructive assay techniques are sought to better characterize spent nuclear fuel. One of the NDA instruments selected for possible deployment is differential die-away self-interrogation (DDSI). The proposed DDSI approach for spent fuel assembly assay utilizes primarily the spontaneous fission and (α, n) neutrons in the assemblies as an internal interrogating radiation source. The neutrons released in spontaneous fission or (α,n) reactions are thermalized in the surrounding water and induce fission in fissile isotopes, thereby creating a measurable signal from isotopes of interest that would be otherwise difficult to measure. The DDSI instrument employs neutron coincidence counting with 3He tubes and list-mode-based data acquisition to allow for production of Rossi-alpha distributions (RADs) in post-processing. The list-mode approach to data collection and subsequent construction of RADs has expanded the analytical possibilities, as will be demonstrated throughout this thesis. One of the primary advantages is that the measured signal in the form of a RAD can be analyzed in its entirety including determination of die-away times in different time domains. This capability led to the development of the early die-away method, a novel leakage multiplication determination method which is tested throughout the thesis on different sources in simulation space and fresh fuel experiments. The early die-away method is a robust, accurate, improved method of determining multiplication without the need for knowledge of the (α,n) source term. The DDSI technique and instrument are presented along with the many novel capabilities enabled by and discovered through RAD analysis. Among the new capabilities presented are the early die-away method, total plutonium content determination, and highly sensitive missing pin detection. Simulation of hundreds of different spent and fresh fuel assemblies were used to develop the analysis algorithms and the techniques were tested on a

  11. ENDF-UTILITY-CODES, codes to check and standardize data in the Evaluated Nuclear Data File (ENDF)

    International Nuclear Information System (INIS)

    Dunford, Charles L.

    2007-01-01

    1 - Description of program or function: The ENDF Utility Codes include 9 codes to check and standardize data in the Evaluated Nuclear Data File (ENDF). Four programs of this release, GETMAT, LISTEF, PLOTEF and SETMDC are no more maintained since release 6.13. The suite of ENDF utility codes includes: - CHECKR (version 7.01) is a program for checking that an evaluated data file conforms to the ENDF format. - FIZCON (version 7.02) is a program for checking that an evaluated data file has valid data and conforms to recommended procedures. - GETMAT (version 6.13) is designed to retrieve one or more materials from an ENDF formatted data file. The output will contain only the selected materials. - INTER (version 7.01) calculates thermal cross sections, g-factors, resonance integrals, fission spectrum averaged cross sections and 14.0 MeV (or other energy) cross sections for major reactions in an ENDF-6 or ENDF-5 format data file. - LISTEF (version 6.13) is designed to produce summary and annotated listings of a data file in either ENDF-6 or ENDF-5 format. - PLOTEF (version 6.13) is designed to produce graphical displays of a data file in either ENDF-5 or ENDF-6 format. The form of graphical output depends on the graphical devices available at the installation where this code will be used. - PSYCHE (version 7.02) is a program for checking the physics content of an evaluated data file. It can recognise the difference between ENDF-5 or ENDF-6 formats and performs its tests accordingly. - SETMDC (version 6.13) is a utility program that converts the source decks of programs to different computers (DOS, UNIX, LINUX, VMS, Windows). - STANEF (version 7.01) performs bookkeeping operations on a data file containing one or more material evaluations in ENDF format. The version 7.02 of the ENDF Utility Codes corrects all bugs reported to NNDC as of April 1, 2005 and supersedes all previous releases. Three codes CHECKR, STANEF, and INTER were actually ported from the 7.01 release

  12. Nuclear Knowledge and Competence: Fundamental Prerequisites for the Safe Utilization of Radiation Sources in a Small Non-Nuclear Country — Experience of Montenegro

    International Nuclear Information System (INIS)

    Jovanovic, S.; Dlabac, A.

    2016-01-01

    Provision of adequate knowledge, competence and expertise represents a major concern when addressing nuclear and radiation safety issues in small countries — if inadequate, safety will eventually be jeopardized. Montenegro is such a small, developing and “nonnuclear” country—the use of radiation sources being modest and limited to a few ordinary applications (primarily in health care). Even though, there is (or will be in the foreseeable future) a significant need in nuclear knowledge, competence and expertise — directly or indirectly related to nuclear/radiation safety and security issues. It goes about the following, the list being not exhaustive: (i) medical applications (diagnostics, radiotherapy, palliation, sterilization of equipment, consumables, blood products, etc.), (ii) radiation protection, including various dosimetry services and QC/QA of radiation sources; (iii) environmental protection (radioecology, analytical and monitoring services, etc.), (iv) low and medium activity radioactive waste management (including a newly licenced storage), (v) industrial, geological, hydrological, agricultural, biochemical and archaeological applications (non-destructive testing, various gauges, radioisotope labeling, harmful insects sterilization, etc.), (vi) scientific and educational uses, (vii) cultural heritage preservation and investigation, (viii) legislative and regulatory aspects, including complying to international safety/security norms and joining international conventions in the field, (ix) preparedness and response to radiological and nuclear emergency situations, (x) combating illicit trafficking of nuclear and other radioactive materials, (xi) nuclear forensics, (xii) security systems based on X-ray and other nuclear methods, (xiii) introduction of some future topics (e.g., nuclear power for electricity generation and sea water desalination), (xiv) public information and communication with media, etc.

  13. Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety.

  14. Nuclear data processing for cross-sections generation for fusion-fission, ADS, and IV generation reactors utilization

    Energy Technology Data Exchange (ETDEWEB)

    Velasquez, Carlos E.; Fernandes, Lorena C.; Pereira, Claubia; Veloso, Maria Auxiliadora F.; Costa, Antonella L. [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear

    2017-11-01

    One of the mains topics about nuclear reactors is the microscopic cross section for incident neutrons. Therefore, in this work, it is evaluated the microscopic and macroscopic cross section for a nuclide and a material. One of the nuclides microscopic cross-section studied is the {sup 56}Fe which is the highest compound from the material macroscopic cross section studied SS316. On the other hand, it was studied the microscopic cross section of the {sup 242}Pu which is one of the nuclides that composes the nuclear fuel. The nuclear fuel chosen is a spent fuel reprocessed by UREX+ technique and spiked with thorium with 20% of fissile material. Therefore it was studied the macroscopic cross section from this nuclear fuel. Both of them were compared by using three different ways to reprocess the nuclides, one for LWR, another for ADS and the last one for Fusion reactors. The library used was JEFF-3.2 recommend for the reactors studied. The comparison was made at 1200 K for the nuclear fuel and 700K for the SS316.The results present differences due to the energy discretization, the number of groups chosen for each reactor and some nuclear reactions taken into consideration according to the neutron spectrum for each reactor. The nuclides were processed by NJOY99.364 and plotted with MCNP-Vised. (author)

  15. Nuclear data processing for cross-sections generation for fusion-fission, ADS, and IV generation reactors utilization

    International Nuclear Information System (INIS)

    Velasquez, Carlos E.; Fernandes, Lorena C.; Pereira, Claubia; Veloso, Maria Auxiliadora F.; Costa, Antonella L.

    2017-01-01

    One of the mains topics about nuclear reactors is the microscopic cross section for incident neutrons. Therefore, in this work, it is evaluated the microscopic and macroscopic cross section for a nuclide and a material. One of the nuclides microscopic cross-section studied is the 56 Fe which is the highest compound from the material macroscopic cross section studied SS316. On the other hand, it was studied the microscopic cross section of the 242 Pu which is one of the nuclides that composes the nuclear fuel. The nuclear fuel chosen is a spent fuel reprocessed by UREX+ technique and spiked with thorium with 20% of fissile material. Therefore it was studied the macroscopic cross section from this nuclear fuel. Both of them were compared by using three different ways to reprocess the nuclides, one for LWR, another for ADS and the last one for Fusion reactors. The library used was JEFF-3.2 recommend for the reactors studied. The comparison was made at 1200 K for the nuclear fuel and 700K for the SS316.The results present differences due to the energy discretization, the number of groups chosen for each reactor and some nuclear reactions taken into consideration according to the neutron spectrum for each reactor. The nuclides were processed by NJOY99.364 and plotted with MCNP-Vised. (author)

  16. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

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

  17. Authorization process in the sphere of nuclear fuel utilization according to the Bulgarian Act on the Safe Use of Nuclear Energy

    International Nuclear Information System (INIS)

    Stoyanova, P.; Vitkova, M.; Elenkov, D.; Vapirev, E.

    2003-01-01

    The new Bulgarian Act on the Safe Use of Nuclear Energy (ASUNE) was adopted in the year 2002. It replaced the former Act on the Use of Nuclear Energy for Peaceful Purposes, which was in force for about 17 years. The ASUNE covers the activities involving nuclear energy and sources of ionizing radiation mainly by establishing a consistent authorization regime. It is an up-to-date act, based on the IAEA requirements and standards, and yet fully in compliance with the Bulgarian legislative system. The newly adopted Act is based on the following main principles: Priority of safety over economic and other social needs; Occupational and public exposure to ionizing radiation to be kept as low as reasonably achievable (ALARA); Direct and personal liability of the licensee/permit holder; Independence of the regulatory body; Application of a less prescriptive approach; Issuing of authorizations under conditions of legal equality and transparency

  18. Study on the utilization of the cognitive architecture EPIC to the task analysis of a nuclear power plant operator

    International Nuclear Information System (INIS)

    Soares, Herculano Vieira

    2003-02-01

    This work presents a study of the use of the integrative cognitive architecture EPIC - Executive-Process - Interactive-Control, designed to evaluate the performance of a person performing tasks in parallel in a man-machine interface, as a methodology for Cognitive Task Analysis of a nuclear power plant operator. A comparison of the results obtained by the simulation by EPIC and the results obtained by application of the MHP model to the tasks performed by a shift operator during the execution of the procedure PO-E-3 - Steam Generator Tube Rupture of Angra 1 Nuclear Power Plant is done. To subsidize that comparison, an experiment was performed at the Angra 2 Nuclear Power Plant Full Scope Simulator in which three operator tasks were executed, its completion time measured and compared with the results of MHP and EPIC modeling. (author)

  19. Seismic PSA implementation standards by AESJ and the utilization of the advanced safety examination guideline for seismic design for nuclear power plant

    International Nuclear Information System (INIS)

    Ebisawa, Katsumi; Hibino, Kenta

    2008-01-01

    The Advanced Safety Examination Guideline for Seismic Design for Nuclear Power Plant (the advanced safety examination guideline) was worked out on September 19, 2006. In this paper, a summary of the method of probability theory in the advanced safety examination guideline and the Seismic PSA Implementation Standards is stated. On utilization of the probability theory for the advanced safety examination guideline, the uncertainty resulting from the process of the decision of the basic design earthquake ground motion (Ss) is stated to be considered using the proper method. The references of the extra probability for evaluation of earthquake hazard and combination of the working load and the earthquake load are stated. Definition, evaluation method and effort to lower the 'residual risks', and relation between the residual risks and the extra probability of Ss are described. A summary of the earthquake-resistant design for nuclear power facilities is explained by the old guideline. (S.Y.)

  20. The utility of system-level RAM analysis and standards for the US nuclear waste management system

    International Nuclear Information System (INIS)

    Rod, S.R.; Adickes, M.D.; Paul, B.K.

    1992-03-01

    The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing a system to manage spent nuclear fuel and high-level radioactive waste in accordance with the Nuclear Waste Policy Act of 1982 and its subsequent amendments. Pacific Northwest Laboratory (PNL) is assisting OCRWM in its investigation of whether system-level reliability, availability, and maintainability (RAM) requirements are appropriate for the waste management system and, if they are, what appropriate form should be for such requirements. Results and recommendations are presented

  1. Utility of Social Modeling for Proliferation Assessment - Enhancing a Facility-Level Model for Proliferation Resistance Assessment of a Nuclear Enegry System

    Energy Technology Data Exchange (ETDEWEB)

    Coles, Garill A.; Brothers, Alan J.; Gastelum, Zoe N.; Olson, Jarrod; Thompson, Sandra E.

    2009-10-26

    The Utility of Social Modeling for Proliferation Assessment project (PL09-UtilSocial) investigates the use of social and cultural information to improve nuclear proliferation assessments, including nonproliferation assessments, Proliferation Resistance (PR) assessments, safeguards assessments, and other related studies. These assessments often use and create technical information about a host State and its posture towards proliferation, the vulnerability of a nuclear energy system (NES) to an undesired event, and the effectiveness of safeguards. This objective of this project is to find and integrate social and technical information by explicitly considering the role of cultural, social, and behavioral factors relevant to proliferation; and to describe and demonstrate if and how social science modeling has utility in proliferation assessment. This report describes a modeling approach and how it might be used to support a location-specific assessment of the PR assessment of a particular NES. The report demonstrates the use of social modeling to enhance an existing assessment process that relies on primarily technical factors. This effort builds on a literature review and preliminary assessment performed as the first stage of the project and compiled in PNNL-18438. [ T his report describes an effort to answer questions about whether it is possible to incorporate social modeling into a PR assessment in such a way that we can determine the effects of social factors on a primarily technical assessment. This report provides: 1. background information about relevant social factors literature; 2. background information about a particular PR assessment approach relevant to this particular demonstration; 3. a discussion of social modeling undertaken to find and characterize social factors that are relevant to the PR assessment of a nuclear facility in a specific location; 4. description of an enhancement concept that integrates social factors into an existing, technically

  2. Utility training

    International Nuclear Information System (INIS)

    Villaros, P.E.; Luxo, Armando; Bruant, Jacques

    1977-01-01

    The study of operational training systems for electro-nuclear utilities may be conducted through two different approaches. A first analytical approach consists of determining, for each position of a given organization chart, the necessary qualifications required and the corresponding complementary training to be provided. This approach applies preferentially to existing classical systems which are converted to nuclear operation with objectives of minimum structural changes and conservation of maximum efficiency. A second synthetical approach consists of determining the specific characteristics of nuclear plant operation, then, of deducting the training contingencies and the optimized organization chart of the plant, while taking into account, at each step, the parameters linked to local conditions. This last approach is studied in some detail in the present paper, taking advantage of its better suitability to the problems raised at the first stage of an electro-nuclear program development. In this respect, the possibility offered by this apprach to coordinate the training system of a given nuclear power station personnel with the overall problem of developing a skilled industrial labor force in the country, may lead to reconsideration of some usual priorities in the economy of operation of the nuclear power plant

  3. Stabilization of the outputs of pulse amplifiers utilizing non-linear feedback networks. Application to nuclear spectrometer amplifiers

    International Nuclear Information System (INIS)

    Henein, K.L.

    1978-02-01

    In nuclear spectroscopy, baseline instability and random fluctuations at the output of the amplifier create imperfectly solved problems mainly at high counting rates. After a critical examination of current systems, solutions are proposed which surpass existing ones. It is shown that restorers and stabilizers of baselines have their own preferential application. Considering natural limits of performance the proposed solutions give entirely satisfactory results [fr

  4. Utilities objectives

    International Nuclear Information System (INIS)

    Cousin, Y.; Fabian, H.U.

    1996-01-01

    The policy of French and german utilities is to make use of nuclear energy as a long term, competitive and environmentally friendly power supply. The world electricity generation is due to double within the next 30 years. In the next 20 to 30 years the necessity of nuclear energy will be broadly recognized. More than for most industries, to deal properly with nuclear energy requires the combination of a consistent political will, of a proper institutional framework, of strong and legitimate control authorities, of a sophisticated industry and of operators with skilled management and human resources. One of the major risk facing nuclear energy is the loss of competitiveness. This can be achieved only through the combination of an optimized design, a consistent standardization, a proper industrial partnership and a stable long term strategy. Although the existing plants in Western Europe are already very safe, the policy is clearly to enhance the safety of the next generation of nuclear plants which are designing today. The French and German utilities have chosen an evolutionary approach based on experience and proven technologies, with an enhanced defense in depth and an objective of easier operation and maintenance. The cost objective is to maintain and improve what has been achieved in the best existing power plants in both countries. This calls for rational choices and optimized design to meet the safety objectives, a strong standardization policy, short construction times, high availability and enough flexibility to enable optimization of the fuel cycle throughout the lifetime of the plants. The conceptual design phase has proven that the French and German teams from industry and from the utilities are able to pursue both the safety and the cost objectives, basing their decision on a rational approach which could be accepted by the safety authorities. (J.S.)

  5. Use of nuclear techniques for mutation and selection of fungi for high protein yield utilizing carbon from inexpensive agricultural waste

    International Nuclear Information System (INIS)

    Georgopulos, S.

    1976-12-01

    The report briefly describes work carried out on the following subjects: Determination of protein in fungal strains (including Fusarium and Aspergillus niger); induction and selection of mutants (Aspergillus niger) giving higher yields of biomass and/or higher protein content; ability of fungi (Candida tropicalis) to utilize water extracts of carob bean pods; growth of Fusarium monoliforme at the expense of carob sugars; the use of alternate oxidase-negative mutants (of Ustilago maydis), for better utilization of substrates for growth (electron transport pathways in reoxidation of reduced coenzymes); kinetics of batch and continuous cultivation of Fusarium moniliforme (cultivated on aqueous carob extracts)

  6. Insight into structure and assembly of the nuclear pore complex by utilizing the genome of a eukaryotic thermophile

    DEFF Research Database (Denmark)

    Amlacher, Stefan; Sarges, Phillip; Flemming, Dirk

    2011-01-01

    is composed of two large Nups, Nup192 and Nup170, which are flexibly bridged by short linear motifs made up of linker Nups, Nic96 and Nup53. This assembly illustrates how Nup interactions can generate structural plasticity within the NPC scaffold. Our findings therefore demonstrate the utility of the genome...

  7. The study on the role of very high temperature reactor and nuclear process heat utilization in future energy systems

    International Nuclear Information System (INIS)

    Yasukawa, Shigeru; Mankin, Shuichi; Sato, Osamu; Tadokoro, Yoshihiro; Nakano, Yasuyuki; Nagano, Takao; Yamaguchi, Kazuo; Ueno, Seiichi.

    1987-11-01

    The objectives of the systems analysis study on ''The Role of High Temperature Nuclear Heat in Future Energy Systems'' under the cooperative research program between Japan Atomic Energy Research Institute and the Massachusetts Institute of Technology are to analyze the effect and the impact of introduction of high temperature nuclear heat in Japanese long-term energy systems aiming at zero environmental emissions from view points of energy supply/demand, economy progress, and environmental protection, and to show the potentials of involved technologies and to extract the associated problems necessary for research and developments. This report describes the results being obtained in these three years from 1985. The present status of our energy system are explained at first, then, our findings concerning on analytical approach, method for analysis, view points to the future, scenario state space, reference energy systems, evolving technologies in it, and results analyzed are described. (author)

  8. US nuclear power generation the historical aspect of broad and stable utilization as the pioneer and the art of commissioning

    International Nuclear Information System (INIS)

    Watanabe, Kazuo

    2009-01-01

    The US has been making application of over 100 units of nuclear power generation from early 1957 as pioneer. On the other hand about 30 units are forced to be shut down. Nuclear units are also honorably given the political part by several Presidents at international stage in the history. In the unaccustomed period they were unable to avoid unwilling experience, as Three Mile Island and Indian Point. These are requesting the refinement of designing technology. US are facing aging of installed units and great duties for further development. That will be realization of more advanced reactors, high operational and administrative ability, establishment of efficient and stable fuel cycles, and process of long period of decommissioning. The art of commissioning is expected its smart usage at wide range of this technology. (author)

  9. Rational power utilization and generation without nuclear energy: Potentials and assessment of effects on the power industry, ecology, and economy

    International Nuclear Information System (INIS)

    Masuhr, K.P.; Eckerle, K.; Hofer, P.; Meckel, H.; Wolff, H.; Frey, B.; Schilling, K.; Brand, M.; Jochem, E.

    1987-10-01

    The unabridged version of the investigation gives the reader interested in details the relevant information on the individual analyses. The development of the investigation describes the analysis of the demographical and economical framework data, the long-term development of the energy price and the long-term energy demand development in a reference scenario. As most important status-quo condition it is defined that the development lines to be expected of the expected fuel and power demand and the supply of the power demand are indicated under the condition of further development of the nuclear power generation being borne by a political consensus. A contrast scenario examines if replacement of the nuclear energy would be possible by power cuts, development of the local heat supply and long-distance heat supply by cogeneration systems and development of the industrial cogeneration systems. (DG) [de

  10. Utilization of dose assessment models to facilitate off-site recovery operations for accidents at nuclear facilities

    International Nuclear Information System (INIS)

    Dickerson, M.H.; Foster, K.T.

    1989-09-01

    One of the most important uses of dose assessment models in response to accidents at nuclear facilities is to help provide guidance to emergency response managers for identifying, and mitigating, the consequences of an accident once the accident has been terminated. By combining results from assessment models with radiological measurements, a qualitative methodology can be developed to aid emergency response managers in determining the total dose received by the population and to minimize future doses through the use of mitigation procedures. To illustrate the methodology, this discussion focuses on the use of models to estimate the dose delivered to the public both during and after a nuclear accident. 4 refs., 10 figs., 1 tab

  11. Economic analysis of energy system considering the uncertainties of crude oil, natural gas and nuclear utilization employing stochastic dynamic programming

    International Nuclear Information System (INIS)

    Hasegawa, Keita; Komiyama, Ryoichi; Fujii, Yasumasa

    2016-01-01

    The paper presents an economic rationality analysis of power generation mix by stochastic dynamic programming considering fuel price uncertainties and supply disruption risks such as import disruption and nuclear power plant shutdown risk. The situation revolving around Japan's energy security adopted the past statistics, it cannot be applied to a quantitative analysis of future uncertainties. Further objective and quantitative evaluation methods are required in order to analyze Japan's energy system and make it more resilient in sight of long time scale. In this paper, the authors firstly develop the cost minimization model considering oil and natural gas price respectively by stochastic dynamic programming. Then, the authors show several premises of model and an example of result with related to crude oil stockpile, liquefied natural gas stockpile and nuclear power plant capacity. (author)

  12. Japanese utilities' plutonium utilization program

    International Nuclear Information System (INIS)

    Matsuo, Yuichiro.

    1996-01-01

    Japan's 10 utility companies are working and will continue to work towards establishing a fully closed nuclear fuel cycle. The key goals of which are: (1) reprocessing spent fuel; (2) recycling recovered uranium and plutonium; and (3) commercializing fast breeder technology by around the year 2030. This course of action by the Japanese electric power industry is in full accordance with Japan's national policy outlined in the government's report ''The Long-Term Program for Research, Development, and Nuclear Energy,'' which was published in June 1994. The Japanese civilian nuclear program is a long-term program that looks into the 21st century and beyond. It is quite true that sustaining the recycling option for energy security and the global environment demands a large investment. For it to be accepted by the public, safety must be the highest priority and will be pursued at a great cost if necessary. In its history, Japan has learned that as technology advances, costs will come down. The Japanese utility industry will continue investment in technology without compromising safety until the recycling option becomes more competitive with other options. This effort will be equally applied to the development of the commercial FBRs. The Japanese utility industry is confident that Japan's stable policy and strong objective to develop competitive and peaceful technology will contribute to the global economy and the environment without increasing the threat of plutonium proliferation

  13. IMP2, a nuclear gene controlling the mitochondrial dependence of galactose, maltose and raffinose utilization in Saccharomyces cerevisiae.

    Science.gov (United States)

    Donnini, C; Lodi, T; Ferrero, I; Puglisi, P P

    1992-02-01

    The IMP2 gene of Saccharomyces cerevisiae is involved in the nucleo-mitochondrial control of maltose, galactose and raffinose utilization as shown by the inability of imp2 mutants to grow on these carbon sources in respiratory-deficient conditions or in the presence of ethidium bromide and erythromycin. The negative phenotype cannot be scored in the presence of inhibitors of respiration and oxidative phosphorylation, indicating that the role of the mitochondria in the utilization of the above-mentioned carbon sources in imp2 mutants is not at the energetical level. Mutations in the IMP2 gene also confer many phenotypic alterations in respiratory-sufficient conditions, e.g. leaky phenotype on oxidizable carbon sources, sensitivity to heat shock and sporulation deficiency. The IMP2 gene has been cloned, sequenced and disrupted. The phenotype of null imp2 mutants is indistinguishable from that of the originally isolated mutant.

  14. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  15. Feasibility analysis of the utilization of moderator heat for agricultural and aquacultural purposes, Bruce nuclear power development

    International Nuclear Information System (INIS)

    1977-12-01

    A study is presented of the feasibility of using moderator reject heat from the Bruce nuclear power development either to heat greenhouses or to aid in a warm water hatchery or aquaculture operation. The study examines heat extraction and delivery plans, reliability of supply, pricing schedules, the Ontario greenhouse industry, site selection criteria, water transmission and distribution, costs, approvals required, and a construction timetable. Total system analysis shows that a greenhouse facility would be viable but the aquaculture/hatchery scheme is more cost-effective. (E.C.B.)

  16. National phantoms bank for the service of nuclear medicine in Cuba. Utility for the quality control of the instrumentation

    International Nuclear Information System (INIS)

    Varela C, C.; Diaz B, M.; Lopez B, G.M.

    2006-01-01

    Although, most of the applications in Nuclear Medicine have diagnostic ends, its going enlarging considerably the therapeutic applications. So that the diagnostic accuracy or the therapy effectiveness have not been affected, it becomes indispensable the quality control of the instrumentation, independently of its technological complexity and/or its exploitation period. Before the real lack of phantoms in the institutions, it was created a bank that puts to disposition of all the institutions, the existent phantoms in the country, and those that are going acquired, centralized by the State Control of Medical Equipment Center (CCEEM) and with Web access in its place www.eqmed.sld.cu. Having like base the elaboration of the National Protocol for the Quality Control of the Instrumentation in Nuclear Medicine that keeps in mind the international normative and the own existent conditions, were dictated and established two national regulations and its are being carried out the first audits to the instrumentation quality. These have evidenced the partial realization of the established quality controls in the services, the necessity to make aware as for the fulfillment of the criteria and quality concepts for the instrumentation, as well as the necessity to increase the phantoms number to the bank to guarantee the fulfillment of the Quality Control Programs. (Author)

  17. Improving nuclear utility generation capacity, understanding the sources of forced outage and learning how to prevent them

    International Nuclear Information System (INIS)

    Brodeur, D.L.; Todreas, N.E.; Angus, V.T.

    1998-01-01

    MIT and PECO Energy have completed a detailed examination of the sources of forced outages at the Limerick Generating Station (LGS) Boiling Water Reactor Class IV (BWR IV) site over a five year period and contrasted that information to similar BWR IV utilities in the United States over the same period. Each forced outage was attributed to one system and assigned causal codes of equipment versus human factors and failure attributes such as weak design, poor craftsmanship, and worn parts. It was found that fifty four percent of the lost power at LGS was the result of Balance of Plant failures. Industry wide data identifies fifty nine percent of the lost power as attributed to Balance of Plant failures. Balance of Plant systems are those systems not included in the primary and safety related system category. Considering failure causal factors, forty six percent of the lost power at the utility under study was the result of equipment factors such as weak design or worn parts. Significantly, the study showed a high variance between those systems which caused significant forced outage at the two sister LGS units. This demonstrated the infrequent nature of plant forced outages within a given system. This was supported by the observation that dominant systems attributing to forced outage at LGS were not equally represented in industry data. It is suggested that for individual utilities to dramatically improve unit capability factors with regard to Balance of Plant systems, they must learn from industry wide experiences and develop cooperative means of exchanging lessons learned among similarly designed plants and systems. With the broad knowledge base of system failures, current designs must be frequently assessed and altered until each system poses an acceptable level of risk to generation capacity. (author)

  18. Trends in Japan's power generation costs after the Fukushima Daiichi Nuclear Power Plant accident and their influence on finance of electric utilities

    International Nuclear Information System (INIS)

    Matsuo, Yuhji; Yamaguchi, Yuhji; Murakami, Tomoko

    2013-01-01

    Following the Fukushima Daiichi nuclear power plant accident, the nuclear reactors that were suspended for periodic inspections after the Fukushima accident were not permitted to resume operation, and nuclear power generation in Japan continued to decline. In this article, the authors quantitatively evaluated the effects on power generation costs of Japan's situation, using electric utilities financial reports up to FY 2011. We also analyzed the profitability of the Japanese electric industry, using the financial statements included in the reports, and quantitatively evaluated the effects of changes in power generation costs. The total cost of power generation has increased from 7.5 trillion yen in FY 2010 before the Fukushima accident to 9.6 trillion yen in FY 2011 and to 10.6 trillion yen in FY 2012. In particular, the fuel cost for thermal power generation rose sharply from 3.7 trillion yen in FY 2010 to 6.1 trillion yen in FY 2011 and 7.3 trillion yen in FY 2012, almost doubling in the two years from FY 2010 to 2012. The unit cost of power generation rose sharply from 8.6 yen/kWh in FY 2010 to 11.8 yen/kWh in FY 2011 and 13.5 yen/kWh in FY 2012. The unit cost is expected to rise even further in FY 2013 due to the weak yen. As the result not only Tokyo Electric Power Company, but also the other general electric utilities registered huge net losses. Their retained earnings (total of eight utilities) dropped by 2 trillion yen between FY 2010 and 2012. With increased thermal power generation, the risk of rising costs associated with changes in primary energy prices and exchange rates has increased drastically. For the stability of the electricity industry and the development of the Japanese economy, the government should clearly formulate a basic policy regarding the composition of power sources, and an effective plan both at home and abroad, and should develop a system that will be also to handle sudden changes in the composition of power sources. (author)

  19. Theoretical-experimental assessment of the variables affecting fretting of Atucha I nuclear power plant utility steam generators tubes

    International Nuclear Information System (INIS)

    Kulichevsky, Raul M.

    1995-01-01

    Fretting wear of Steam Generator tubes caused by flow induced vibrations generates uncertainty on their integrity. The knowledge of the controlling variables of the wear process may give a criterion to evaluate the tubes residual life. Information on vibratory response and dynamic interaction between tubes and their supports are prerequisites for understanding the relationship between fretting wear and tube vibration. Experimental results of the vibratory response of an Atucha-I nuclear power plant type U-tube, the influence of tube/support clearance on this response and a study of tube/support dynamic interaction, which allow the verification of a finite element model of this type of tubes, are presented in this work. Also wear results for the Incoloy 800/DIN 1.4550 austenitic stainless steel pair of materials and a first evaluation of the wear constant of this pair are presented. (author)

  20. REIMR - A Process for Utilizing Liquid Rocket Propulsion-Oriented 'Lessons Learned' to Mitigate Development Risk in Nuclear Thermal Propulsion

    International Nuclear Information System (INIS)

    Ballard, Richard O.

    2006-01-01

    This paper is a summary overview of a study conducted at the NASA Marshall Space Flight Center (NASA-MSFC) during the initial phases of the Space Launch Initiative (SLI) program to evaluate a large number of technical problems associated with the design, development, test, evaluation and operation of several major liquid propellant rocket engine systems (i.e., SSME, Fastrac, J-2, F-1). One of the primary results of this study was the identification of the 'Fundamental Root Causes' that enabled the technical problems to manifest, and practices that can be implemented to prevent them from recurring in future propulsion system development efforts, such as that which is currently envisioned in the field of nuclear thermal propulsion (NTP). This paper will discus the Fundamental Root Causes, cite some examples of how the technical problems arose from them, and provide a discussion of how they can be mitigated or avoided in the development of an NTP system

  1. Design Study of Modular Nuclear Power Plant with Small Long Life Gas Cooled Fast Reactors Utilizing MOX Fuel

    Science.gov (United States)

    Ilham, Muhammad; Su'ud, Zaki

    2017-01-01

    Growing energy needed due to increasing of the world’s population encourages development of technology and science of nuclear power plant in its safety and security. In this research, it will be explained about design study of modular fast reactor with helium gas cooling (GCFR) small long life reactor, which can be operated over 20 years. It had been conducted about neutronic design GCFR with Mixed Oxide (UO2-PuO2) fuel in range of 100-200 MWth NPPs of power and 50-60% of fuel fraction variation with cylindrical pin cell and cylindrical balance of reactor core geometry. Calculation method used SRAC-CITATION code. The obtained results are the effective multiplication factor and density value of core reactor power (with geometry optimalization) to obtain optimum design core reactor power, whereas the obtained of optimum core reactor power is 200 MWth with 55% of fuel fraction and 9-13% of percentages.

  2. Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1983-08-01

    Nuclear byproducts are a major national resource that has yet to be incorporated into the economy. The current Defense Byproducts Program is designed to match specific military and commercial needs with the availability of valuable products which are currently treated as waste at considerable expense in waste management costs. This program plan focuses on a few specific areas with the greatest potential for near-term development and application. It also recognizes the need for a continuing effort to develop new applications for byproducts and to continue to assess the impacts on waste management. The entire program has been, and will continue to be structured so as to ensure the safety of the public and maintain the purity of the environment. Social and institutional concerns have been recognized and will be handled appropriately. A significant effort will be undertaken to inform the public of the benefits of byproduct use and of the care being taken to ensure safe, efficient operation

  3. Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 1. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1983-08-01

    Nuclear byproducts are a major national resource that has yet to be incorporated into the economy. The current Defense Byproducts Program is designed to match specific military and commercial needs with the availability of valuable products which are currently treated as waste at considerable expense in waste management costs. This program plan focuses on a few specific areas with the greatest potential for near-term development and application. It also recognizes the need for a continuing effort to develop new applications for byproducts and to continue to assess the impacts on waste management. The entire program has been, and will continue to be structured so as to ensure the safety of the public and maintain the purity of the environment. Social and institutional concerns have been recognized and will be handled appropriately. A significant effort will be undertaken to inform the public of the benefits of byproduct use and of the care being taken to ensure safe, efficient operation.

  4. Efficacy of clinical diagnostic procedures utilized in nuclear medicine. Technical progress report, 1 December 1981-30 November 1982

    International Nuclear Information System (INIS)

    Saenger, E.L.

    1982-07-01

    The efficacy of nuclear medicine diagnostic procedures was measured. Three levels of efficacy were defined. However, two different methods of evaluating efficacy itself were first compared. Using two methods, logistic regression and entropy-minimax pattern detection, substantial agreement was found between them in several clinical observations. (1) There are no attributes that indicate that any grouping of symptoms, signs, and laboratory findings is capable of suggesting that a patient does or does not have a pulmonary embolus. (2) The lung scan test is the only reliable method which indicates that a patient may have a pulmonary embolus or does not have a pulmonary embolus. (3) The validity of these conclusions and the ability to apply them widely to ongoing clinical practice is based on the prospective design of the Study which included an appropriate distribution of institutions by type, size, and geographic location. Also, the only judgement samples was that of the referring physician

  5. REIMR - A Process for Utilizing Liquid Rocket Propulsion-Oriented 'Lessons Learned' to Mitigate Development Risk in Nuclear Thermal Propulsion

    Science.gov (United States)

    Ballard, RIchard O.

    2006-01-01

    This paper is a summary overview of a study conducted at the NASA Marshall Space Flight Center (NASA MSFC) during the initial phases of the Space Launch Initiative (SLI) program to evaluate a large number of technical problems associated with the design, development, test, evaluation and operation of several major liquid propellant rocket engine systems (i.e., SSME, Fastrac, J-2, F-1). One of the primary results of this study was the identification of the Fundamental Root Causes that enabled the technical problems to manifest, and practices that can be implemented to prevent them from recurring in future propulsion system development efforts, such as that which is currently envisioned in the field of nuclear thermal propulsion (NTF). This paper will discuss the Fundamental Root Causes, cite some examples of how the technical problems arose from them, and provide a discussion of how they can be mitigated or avoided in the development of an NTP system

  6. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  7. PWR in-core nuclear fuel management optimization utilizing nodal (non-linear NEM) generalized perturbation theory

    International Nuclear Information System (INIS)

    Maldonado, G.I.; Turinsky, P.J.; Kropaczek, D.J.

    1993-01-01

    The computational capability of efficiently and accurately evaluate reactor core attributes (i.e., k eff and power distributions as a function of cycle burnup) utilizing a second-order accurate advanced nodal Generalized Perturbation Theory (GPT) model has been developed. The GPT model is derived from the forward non-linear iterative Nodal Expansion Method (NEM) strategy, thereby extending its inherent savings in memory storage and high computational efficiency to also encompass GPT via the preservation of the finite-difference matrix structure. The above development was easily implemented into the existing coarse-mesh finite-difference GPT-based in-core fuel management optimization code FORMOSA-P, thus combining the proven robustness of its adaptive Simulated Annealing (SA) multiple-objective optimization algorithm with a high-fidelity NEM GPT neutronics model to produce a powerful computational tool used to generate families of near-optimum loading patterns for PWRs. (orig.)

  8. Training for the seismic qualification utility group (SQUG) generic implementation procedure (GIP) for verification of seismic effects on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Schaffstall, R.E.; Smith, N.P.; Baker, K.M.

    1993-01-01

    Resolution of USI A-46 was accomplished May, 1992 with the issuance of the SER for the GIP, Revision 2. The implementation of the resolution for the SQUG plants will be completed by 1996. Both the USNRC and the SQUG utilities have expended considerable resources to effect a common understanding that the effort has been worth the price. The Training Program developed to ensure that the efforts expended by the SQUG was indeed worth the price will be a major contributor in the success of the implementation. All of the older nuclear power plants in the United States now have an alternative standard to determine seismic resistance using experience data- a standard against which they can be evaluated and found seismically adequate to achieve and maintain a safe and reliable shutdown when subjected to strong motion earthquakes

  9. A multi-attribute utility decision analysis for treatment alternatives for the DOE/SR aluminum-based spent nuclear fuel

    International Nuclear Information System (INIS)

    Davis, Freddie J.; Weiner, Ruth Fleischman; Wheeler, Timothy A.; Sorenson, Ken B.; Kuzio, Kenneth A.

    2000-01-01

    A multi-attribute utility analysis is applied to a decision process to select a treatment method for the management of aluminum-based spent nuclear fuel (Al-SNF) owned by the US Department of Energy (DOE). DOE will receive, treat, and temporarily store Al-SNF, most of which is composed of highly enriched uranium, at its Savannah River Site in South Carolina. DOE intends ultimately to send the treated Al-SNF to a geologic repository for permanent disposal. DOE initially considered ten treatment alternatives for the management of Al-SNF, and has narrowed the choice to two of these: the direct disposal and melt and dilute alternatives. The decision analysis presented in this document focuses on a formal decision process used to evaluate these two remaining alternatives

  10. Improved sample utilization in thermal ionization mass spectrometry isotope ratio measurements: refined development of porous ion emitters for nuclear forensic applications

    Energy Technology Data Exchange (ETDEWEB)

    Baruzzini, Matthew Louis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-05-08

    The precise and accurate determination of isotopic composition in nuclear forensic samples is vital for assessing origin, intended use and process history. Thermal ionization mass spectrometry (TIMS) is widely accepted as the gold standard for high performance isotopic measurements and has long served as the workhorse in the isotopic ratio determination of nuclear materials. Nuclear forensic and safeguard specialists have relied heavily on such methods for both routine and atypical e orts. Despite widespread use, TIMS methods for the assay of actinide systems continue to be hindered by poor ionization e ciency, often less than tenths of a percent; the majority of a sample is not measured. This represents a growing challenge in addressing nextgeneration nuclear detection needs by limiting the ability to analyze ultratrace quantities of high priority elements that could potentially provide critical nuclear forensic signatures. Porous ion emitter (PIE) thermal ion sources were developed in response to the growing need for new TIMS ion source strategies for improved ionization e ciency, PIEs have proven to be simple to implement, straightforward approach to boosting ion yield. This work serves to expand the use of PIE techniques for the analysis of trace quantities of plutonium and americium. PIEs exhibited superior plutonium and americium ion yields when compared to direct lament loading and the resin bead technique, one of the most e cient methods for actinide analysis, at similar mass loading levels. Initial attempts at altering PIE composition for the analysis of plutonium proved to enhance sample utilization even further. Preliminary investigations of the instrumental fractionation behavior of plutonium and uranium analyzed via PIE methods were conducted. Data collected during these initial trial indicate that PIEs fractionate in a consistent, reproducible manner; a necessity for high precision isotope ratio measurements. Ultimately, PIEs methods were applied for

  11. Utilization of mesoscale atmospheric dynamic model PHYSIC as a meteorological forecast model in nuclear emergency response system

    International Nuclear Information System (INIS)

    Nagai, Haruyasu; Yamazawa, Hiromi

    1997-01-01

    It is advantageous for an emergency response system to have a forecast function to provide a time margin for countermeasures in case of a nuclear accident. We propose to apply an atmospheric dynamic model PHYSIC (Prognostic HYdroStatic model Including turbulence Closure model) as a meteorological forecast model in the emergency system. The model uses GPV data which are the output of the numerical weather forecast model of Japan Meteorological Agency as the initial and boundary conditions. The roles of PHYSIC are the interface between GPV data and the emergency response system and the forecast of local atmospheric phenomena within the model domain. This paper presents a scheme to use PHYSIC to forecast local wind and its performance. Horizontal grid number of PHYSIC is fixed to 50 x 50, whereas the mesh and domain sizes are determined in consideration of topography causing local winds at an objective area. The model performance was examined for the introduction of GPV data through initial and boundary conditions and the predictability of local wind field and atmospheric stability. The model performance was on an acceptable level as the forecast model. It was also recognized that improvement of cloud calculation was necessary in simulating atmospheric stability. (author)

  12. Seminar on utilization of nuclear techniques in the agricultural research carried out in FONAIAP. Abstracts and lectures

    International Nuclear Information System (INIS)

    Romero S, Alfredo

    1997-01-01

    The lectures included in this seminar are related to: development and evaluation of prophylactic methods to control the anaplasmosis and babesiosis (babesia bovis) in the livestock; the diagnosis of bovine basesiosis (babesia bovis) by means of the test of ELISA; validation of the kit ELISA (FAO, OIEA, PANAFTOSA) to determine antibodies against the virus of the foot and mouth disease; variability generation in sugar cane for resistance to mosaic viruses and rusts (puccinia melanocephala) by means of the cultivation of explants and irradiated callus; bioavailabilty of deposit phosphates in animal feeding; biological fixation of nitrogen in three tropical feed crops leguminous and its transfer to Brachiaria humidicola in association; unit of stable isotopic N 1 5 analysis; effect of the efficiency of N by use of different forms of fertilizer application in ground, evaluated by means of the isotopic technique and the N absorbed by the cultivation; application of progesterone and testosterone in the diagnose and control of reproduction in crossbreeds animal husbandry; advances in the monitoring of production systems in double purpose cattle raising in the area of Guayabal, Guarico State; aquatic investigations with nuclear energy techniques; development of the Venezuelan Edaphological Bibliographic Database [es

  13. Utilization of actinide as cell active materials. JAERI's nuclear research promotion program, H10-034-1. Contract research

    International Nuclear Information System (INIS)

    Shiokawa, Yoshinobu; Yamamura, Tomoo; Watanabe, Nobutaka; Umekita, Satoshi

    2002-03-01

    The electrochemical properties of U, Np, Pu and Am were discussed from the viewpoint of cell active materials From the thermodynamic properties and the kinetics of electrode reactions, it is found that neptunium in the aqueous system and some uranium complexes in the polar aprotic solvents can be utilized as an active material of the redox flow battery for the electric power storage. Moreover, A new actinide redox battery is proposed in the present article: the galvanic cell is expressed by Electrode(-) |An 3+ , An 4+ | |AnO 2 + , AnO 2 2+ | Electrode(+). The actinide batteries are expected to have more excellent charge and discharge performance than the current vanadium battery because of the great similarity of chemical species in the each redox couple. The standard rate constants and formal potential of Np(VI)/Np(V) and Np(IV)/Np(III) couples were determined by the cyclic voltammetry and the neptunium battery was demonstrated. For the development of uranium redox flow battery, the redox reaction mechanisms and redox potentials of uranium -diketones including new -tetraketones were elucidated and it was found the open circuit voltage is increased with the acid dissociation constant of the ligand. (author)

  14. Concrete-polymer composite materials and their potential for construction, urban waste utilization, and nuclear waste storage

    International Nuclear Information System (INIS)

    Fowler, E.E.; Steinberg, Meyer.

    1974-01-01

    A wide range of concrete-polymer composites have been investigated by Brookhaven National Laboratory. Polymer impregnated concrete (PIC) is basically formed by drying cured conventional concrete, displacing the air from open cell void volume, diffusing low viscosity monomer (less than 10 cps) through the open cell structure, saturating the concrete with the monomer and in-situ polymerizing the monomer to polymer by most convenient means. Mainly free-radical vinyl type monomers are used. For increased thermal stability, crosslinking agents and thermosetting monomers such as styrene-trimethylol propane trimethacrylate (TMPTMA) and polyester-styrene are used. Much informations on the formation, structural properties and durability of PIC have been accumulated over past five years. U.S. Patent 3,567,496 has been issued on the production of PIC. Compressive strength can be increased from 352 kg/cm 2 of conventional concrete to 1,410 kg/cm 2 . Water absorption is reduced by 99% and the freeze-thaw resistance is remarkably improved. With high silica cement, strong basaltic aggregate, and high temperature steam curing, strength increase from 845 to over 2,630 kg/cm 2 can be obtained. A maximum of 238 kg/cm 2 tensile strength has been obtained with the steam-cured concrete. In the steam- cured concrete, polymer loading roughly around 8% by weight is obtained. Aggregates can include the urban solid waste discarded by man. Sewage and solid waste refuse-polymer concrete has been produced by using garbage as aggregate and sewage as the hydrating media for cement. The potentially important application of hydrauric cement concrete, in combination with the polymers in PIC and PC, is the storage of long-living radioactive wastes from nuclear industry. (Iwakiri, K.)

  15. Guidelines and workbook for assessment of organization and administration of utilities seeking operating license for a nuclear power plant. Guidelines for utility organization and administration plan. Volume 1, Revision 1

    International Nuclear Information System (INIS)

    Thurber, J.A.; Olson, J.; Osborn, R.N.; Sommers, P.; Widrig, R.D.

    1986-09-01

    Volumes 1 and 2 of this report are a partial response to the requirements of Item I.B.1.1 of the ''NRC Action Plan Developed as a Result of the TMI-2 Accident,'' NUREG-0660, and are designed to serve as a basis for replacing the earlier NUREG-0731, ''Guidelines for Utility Management Structure and Technical Resources.'' These Guidelines are intended to provide guidance to the user in preparing a written plan for a proposed nuclear organization and administration. The purpose of the Workbook (Vol. 2) is to guide the NRC reviewer through a systematic review and assessment of a proposed organization and administration. It is the NRC's intention to incorporate these Guidelines and Workbook into a future revision of the Standard Review Plan (SRP), NUREG-0800. However, at this time the report is being published so that the material may be used on a voluntary basis by industry to systematically prepare or evaluate their organization or administration plans. Use of the report by the NRC would not occur until after it has been incorpoarted in the SRP

  16. Expected utility without utility

    OpenAIRE

    Castagnoli, E.; Licalzi, M.

    1996-01-01

    This paper advances an interpretation of Von Neumann–Morgenstern’s expected utility model for preferences over lotteries which does not require the notion of a cardinal utility over prizes and can be phrased entirely in the language of probability. According to it, the expected utility of a lottery can be read as the probability that this lottery outperforms another given independent lottery. The implications of this interpretation for some topics and models in decision theory are considered....

  17. The clinical utility of nuclear magnetic resonance spectroscopy: recent in vitro, in vivo animal and clinical observations

    International Nuclear Information System (INIS)

    Blackstock, A. William; Kwock, Lester; Mukherji, Suresh K.; Schiro, Sharon; Tepper, Joel E.

    1995-01-01

    Purpose/Objective: Combined radiation and 5-fluorouracil (5-FU) has resulted in improved outcomes in patients treated with gastrointestinal malignancies and squamous cancers of the head and neck. In our first aim, we proposed that the enhanced cell kill and tumor regression observed with the combination of 5-FU and radiation is related to radiation potentiating the anti-tumor effects of 5-FU. Using fluorine-19 ( 19 F) nuclear magnetic resonance (nmr) we non-invasively determined the tumor clearance rates of 5-FU +/- radiation in an animal model and used this research tool to predict tumor response in patients receiving concurrent radiation and 5-FU therapy. Our second aim was to evaluate the use of proton ( 1 H) nmr spectroscopy to non-invasively determine the spectral characteristics of malignant tumors in the head and neck and liver and correlate these clinical observations with in vitro and in vivo data. Materials and Methods: 1 H and 19 F spectroscopic analysis were performed with a 2.0T Otsuka magnetic resonance imaging and spectroscopy system. 1 H nmr patient studies were done on a clinical 1.5T Philips MR system. In vitro magnetic resonance spectroscopy (MRS) studies were performed on a 11 T Bruker nmr system. Animal experiments for the 19 F nmr studies were performed on 3-6 week old female (Nu/Nu) athymic nude mice. Animals were injected s.c. with 10 6 human colon adenocarcinoma (HT-29) cells. At a tumor size of 1.0 cm, animals in the first group received i.v. 5-FU (100 mg/kg) immediately prior to spectroscopic analysis. Animals in the second group were treated with a single radiation dose of either 2 Gy or 10 Gy just prior to the 5-FU injection and subsequent spectroscopy. Spectroscopic analyses were performed at 20-30 minute intervals for 4-6 hr's. Results: 19 F nmr: A decrease in tumor clearance was observed in tumors pre-treated with a single dose of irradiation (2.0 Gy and 10 Gy). The clearance rate of the 5-FU for non-irradiated animals was 0.0178 min

  18. Tank Operations Contract Construction Management Methodology. Utilizing The Agency Method Of Construction Management To Safely And Effectively Complete Nuclear Construction Work

    International Nuclear Information System (INIS)

    Leso, K.F.; Hamilton, H.M.; Farner, M.; Heath, T.

    2010-01-01

    Washington River Protection Solutions, LLC (WRPS) has faced significant project management challenges in managing Davis-Bacon construction work that meets contractually required small business goals. The unique challenge is to provide contracting opportunities to multiple small business construction subcontractors while performing high hazard work in a safe and productive manner. Previous to the Washington River Protection Solutions, LLC contract, Construction work at the Hanford Tank Farms was contracted to large companies, while current Department of Energy (DOE) Contracts typically emphasize small business awards. As an integral part of Nuclear Project Management at Hanford Tank Farms, construction involves removal of old equipment and structures and installation of new infrastructure to support waste retrieval and waste feed delivery to the Waste Treatment Plant. Utilizing the optimum construction approach ensures that the contractors responsible for this work are successful in meeting safety, quality, cost and schedule objectives while working in a very hazardous environment. This paper describes the successful transition from a traditional project delivery method that utilized a large business general contractor and subcontractors to a new project construction management model that is more oriented to small businesses. Construction has selected the Agency Construction Management Method. This method was implemented in the first quarter of Fiscal Year (FY) 2009, where Construction Management is performed by substantially home office resources from the URS Northwest Office in Richland, Washington. The Agency Method has allowed WRPS to provide proven Construction Managers and Field Leads to mentor and direct small business contractors, thus providing expertise and assurance of a successful project. Construction execution contracts are subcontracted directly by WRPS to small or disadvantaged contractors that are mentored and supported by DRS personnel. Each small

  19. TANK OPERATIONS CONTRACT CONSTRUCTION MANAGEMENT METHODOLOGY UTILIZING THE AGENCY METHOD OF CONSTRUCTION MANAGEMENT TO SAFELY AND EFFECTIVELY COMPLETE NUCLEAR CONSTRUCTION WORK

    Energy Technology Data Exchange (ETDEWEB)

    LESO KF; HAMILTON HM; FARNER M; HEATH T

    2010-01-14

    Washington River Protection Solutions, LLC (WRPS) has faced significant project management challenges in managing Davis-Bacon construction work that meets contractually required small business goals. The unique challenge is to provide contracting opportunities to multiple small business construction subcontractors while performing high hazard work in a safe and productive manner. Previous to the Washington River Protection Solutions, LLC contract, Construction work at the Hanford Tank Farms was contracted to large companies, while current Department of Energy (DOE) Contracts typically emphasize small business awards. As an integral part of Nuclear Project Management at Hanford Tank Farms, construction involves removal of old equipment and structures and installation of new infrastructure to support waste retrieval and waste feed delivery to the Waste Treatment Plant. Utilizing the optimum construction approach ensures that the contractors responsible for this work are successful in meeting safety, quality, cost and schedule objectives while working in a very hazardous environment. This paper describes the successful transition from a traditional project delivery method that utilized a large business general contractor and subcontractors to a new project construction management model that is more oriented to small businesses. Construction has selected the Agency Construction Management Method. This method was implemented in the first quarter of Fiscal Year (FY) 2009, where Construction Management is performed by substantially home office resources from the URS Northwest Office in Richland, Washington. The Agency Method has allowed WRPS to provide proven Construction Managers and Field Leads to mentor and direct small business contractors, thus providing expertise and assurance of a successful project. Construction execution contracts are subcontracted directly by WRPS to small or disadvantaged contractors that are mentored and supported by DRS personnel. Each small

  20. Erythrocytes in muscular dystrophy. Investigation with 31P nuclear magnetic resonance spectroscopy

    International Nuclear Information System (INIS)

    Sarpel, G.; Lubansky, H.J.; Danon, M.J.; Omachi, A.

    1981-01-01

    Phosphorus 31 nuclear magnetic resonance ( 31 P NMR) signals were recorded from intact human erythrocytes for 16 hours. Total phosphate concentration, which was estimated as the sum of the individual 31 P signals, was 25% lower in erythrocytes from men with myotonic dystrophy than in control erythrocytes. The inorganic-phosphate fraction contained the highest average phosphate concentration over the 16-hour period, and made the major contribution to the difference in total phosphate between the two groups. This result was not observed in erythrocytes from either women with myotonic dystrophy or patients with Duchenne's dystrophy and may be due to a change in cell membrane permeability to inorganic phosphate, which leads to lower steady-state concentrations of the intracellular phosphates

  1. Erythrocytes in muscular dystrophy. Investigation with 31P nuclear magnetic resonance spectroscopy

    International Nuclear Information System (INIS)

    Sarpel, G.; Lubansky, H.J.; Danon, M.J.; Omachi, A.

    1981-01-01

    Phosphorus 31 nuclear magnetic resonance (31P NMR) signals were recorded from intact human erythrocytes for 16 hours. Total phosphate concentration, which was estimated as the sum of the individual 31P signals, was 25% lower in erythrocytes from men with myotonic dystrophy than in control erythrocytes. The inorganic-phosphate fraction contained the highest average phosphate concentration over the 16-hour period, and made the major contribution to the difference in total phosphate between the two groups. This result was not observed in erythrocytes from either women with myotonic dystrophy or patients with Duchenne's dystrophy and may be due to a change in cell membrane permeability to inorganic phosphate, which lead to lower steady-state concentrations of the intracellular phosphates

  2. [Radiopharmacokinetics: Utilization of nuclear medicine

    International Nuclear Information System (INIS)

    Wolf, W.

    1989-01-01

    The work performed in the 1986/1989 period can be characterized as one of testing and documenting that the Radiopharmacokinetic technique is both feasible and applicable to human studies, as well as developing spectroscopic methods for undertaking noninvasive human studies. Main accomplishments include studies which: show that drug targeting can be monitored noninvasively using radiolabeled drugs. The study that documented this finding involved an analysis of the comparative kinetics of biodistribution of 195m Pt-cisplatin to brain tumors, when administered intravenously and intra-arterially; show that such differential targeting of Platinum represents a differential quantity of drug and a differential amount of the active component reaching the target site; show that in vivo NMRS studies of drugs are possible, as documented by our studies of 5-fluorouracil; show that 5-fluorouracil can be trapped in tumors, and that such trapping may be directly correlatable to patient response; show that the radiopharmacokinetic technique can also be used effectively for the study of radiopharmaceuticals used for imaging, as documented in our studies with 99m T c -DMSA

  3. (Radiopharmacokinetics: Utilization of nuclear medicine)

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, W.

    1989-01-01

    The work performed in the 1986/1989 period can be characterized as one of testing and documenting that the Radiopharmacokinetic technique is both feasible and applicable to human studies, as well as developing spectroscopic methods for undertaking noninvasive human studies. Main accomplishments include studies which: show that drug targeting can be monitored noninvasively using radiolabeled drugs. The study that documented this finding involved an analysis of the comparative kinetics of biodistribution of {sup 195m}Pt-cisplatin to brain tumors, when administered intravenously and intra-arterially; show that such differential targeting of Platinum represents a differential quantity of drug and a differential amount of the active component reaching the target site; show that in vivo NMRS studies of drugs are possible, as documented by our studies of 5-fluorouracil; show that 5-fluorouracil can be trapped in tumors, and that such trapping may be directly correlatable to patient response; show that the radiopharmacokinetic technique can also be used effectively for the study of radiopharmaceuticals used for imaging, as documented in our studies with {sup 99m}T{sub c}-DMSA.

  4. Steam generation: fossil-fired systems: utility boilers; industrial boilers; boiler auxillaries; nuclear systems: boiling water; pressurized water; in-core fuel management; steam-cycle systems: condensate/feedwater; circulating water; water treatment

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    A survey of development in steam generation is presented. First, fossil-fired systems are described. Progress in the design of utility and industrial boilers as well as in boiler auxiliaries is traced. Improvements in coal pulverizers, burners that cut pollution and improve efficiency, fans, air heaters and economisers are noted. Nuclear systems are then described, including the BWR and PWR reactors, in-core fuel management techniques are described. Finally, steam-cycle systems for fossil-fired and nuclear power plants are reviewed. Condensate/feedwater systems, circulating water systems, cooling towers, and water treatment systems are discussed

  5. Nuclear magnetic resonance studies of lens transparency

    International Nuclear Information System (INIS)

    Beaulieu, C.F.

    1989-01-01

    Transparency of normal lens cytoplasm and loss of transparency in cataract were studied by nuclear magnetic resonance (NMR) methods. Phosphorus ( 31 P) NMR spectroscopy was used to measure the 31 P constituents and pH of calf lens cortical and nuclear homogenates and intact lenses as a function of time after lens enucleation and in opacification produced by calcium. Transparency was measured with laser spectroscopy. Despite complete loss of adenosine triphosphate (ATP) within 18 hrs of enucleation, the homogenates and lenses remained 100% transparent. Additions of calcium to ATP-depleted cortical homogenates produced opacification as well as concentration-dependent changes in inorganic phosphate, sugar phosphates, glycerol phosphorylcholine and pH. 1 H relaxation measurements of lens water at 200 MHz proton Larmor frequency studied temperature-dependent phase separation of lens nuclear homogenates. Preliminary measurements of T 1 and T 2 with non-equilibrium temperature changes showed a change in the slope of the temperature dependence of T 1 and T 2 at the phase separation temperature. Subsequent studies with equilibrium temperature changes showed no effect of phase separation on T 1 or T 2 , consistent with the phase separation being a low-energy process. 1 H nuclear magnetic relaxation dispersion (NMRD) studies (measurements of the magnetic field dependence of the water proton 1/T 1 relaxation rates) were performed on (1) calf lens nuclear and cortical homogenates (2) chicken lens homogenates, (3) native and heat-denatured egg white and (4) pure proteins including bovine γ-II crystallin bovine serum albumin (BSA) and myoglobin. The NMRD profiles of all samples exhibited decreases in 1/T 1 with increasing magnetic field

  6. Nuclear fission

    International Nuclear Information System (INIS)

    Kodama, T.

    1981-01-01

    The nuclear fission process is pedagogically reviewed from a macroscopic-microscopic point of view. The Droplet model is considered. The fission dynamics is discussed utilizing path integrals and semiclassical methods. (L.C.) [pt

  7. H.R. 5433: This Act may be cited as the Nuclear Fuel Utilization and Domestic Production Act of 1988. Introduced in the House of Representatives, One Hundredth Congress, Second Session, September 30, 1988

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    H.R. 5433 is a bill to assist in creating a viable domestic uranium enrichment industry, to insure the maximum economic utilization of the existing diffusion plant assets, to establish mechanisms which would permit the creation of a privately owned corporation to utilize the Federal Government's investment in centrifuge technology and in the centrifuge assets, to establish alternate sources of enrichment supply, so as to create American jobs, to return moneys to the Government and to increase American industrial competitiveness in world wide nuclear fuel sales

  8. Electric utility report '80

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    A collection of brief atricles describes the trends and developments in Canada's electric utilities for the 1980's. Generating stations planned or under construction are listed. The trends in technology discused at a recent Canadian Electrical Association meeting are summarized in such areas as turbine stability control, power line vibration control, system reliability, substations and transformer specifications. Developments in nuclear generation are discussed and compared on the world scale where Japan, for example, has the world's largest nuclear program. Progress on fusion is discussed. In Canada the electric utilities are receiving the support of the comprehensive nuclear R and D program of Atomic Energy of Canada Ltd. New innovations in utility technology such as street lighting contactors, superconductive fault limiters and demand profile analyzers are discussed. (T.I.)

  9. Pareto utility

    NARCIS (Netherlands)

    Ikefuji, M.; Laeven, R.J.A.; Magnus, J.R.; Muris, C.H.M.

    2013-01-01

    In searching for an appropriate utility function in the expected utility framework, we formulate four properties that we want the utility function to satisfy. We conduct a search for such a function, and we identify Pareto utility as a function satisfying all four desired properties. Pareto utility

  10. Elements of an Alternative to Nuclear Power as a Response to the Energy-Environment Crisis in India: Development as Freedom and a Sustainable Energy Utility

    Science.gov (United States)

    Mathai, Manu V.

    2009-01-01

    Even as the conventional energy system is fundamentally challenged by the "energy-environment crisis," its adherents have presented the prospect of "abundant" and purportedly "green" nuclear power as part of a strategy to address the crisis. Surveying the development of nuclear power in India, this article finds that…

  11. Nuclear imaging

    International Nuclear Information System (INIS)

    Miller, J.H.; Reid, B.S.

    1985-01-01

    Nuclear imaging, utilizing relatively low photon energy emitting isotopes, allows an assessment of anatomic configuration and organ function. This method of imaging is predicted on the utilization of physiologically active radioisotope-labeled compounds or biologically active radioisotopes. Localization of such isotopes in normal or abnormal concentrations may be due to varying physiological or pathological mechanisms

  12. Clean energy : nuclear energy world

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-10-15

    This book explains the nuclear engineering to kids with easy way. There are explanations of birth of nuclear energy such as discover of nuclear and application of modern technology of nuclear energy, principles and structure of nuclear power plant, fuel, nuclear waste management, use of radiation for medical treatment, food supplies, industry, utilization of neutron. It indicates the future of nuclear energy as integral nuclear energy and nuclear fusion energy.

  13. Role of the utility

    International Nuclear Information System (INIS)

    Bellin, A.

    1986-03-01

    It is common to say that a nuclear programme needs basic infrastructures such as an appropriate educational system, governmental organizations for regulation, decision and inspection, engineering organizations for design and implementation, industrial infrastructures for manufacturing, erection and commissioning, operation organizations for running and maintaining power plants. This schematic organization is not sufficient to succeed in a nuclear programme: one has to consider very carefully the attribution of responsibilities. It appears, that, among all the different systems which exist in the world for the organization of a nuclear project, it is always the utility which bears the overall responsibility for the implementation of the project. It defines objectives such as production capacity, schedule, price; it takes part in the definition of a national policy for energy supply, for the choice of a type of reactor, for the implementation of a national nuclear industry; it selects sites and conducts feasibility studies including a preliminary project; it participates in the definition of organization charts and selects contractors; it calls for and obtains authorizations from regulatory bodies; it manages the project, coordinates contractors and permanently ensures that goals are attained as regards safety, quality, schedule, costs. The French utility has directly taken charge of all these basic responsibilities and this is commonly considered as a major reason of the success of the French nuclear programme. Depending on its capacities, the utility may delegate some of these responsibilities - mainly concerning engineering and project management - to experienced firms. Nevertheless, one has to remember that the utility bears the final responsibility and that it is probably the organization most fully aware of the fact that the final goal is not the construction of a nuclear power station but the production of nuclear electricity in the best and safest conditions

  14. The acquisition of nuclear power plants and national participation, seen from the point of view of the electrical utilities responsible for construction and operation

    International Nuclear Information System (INIS)

    Trevino Coca, M.

    1978-01-01

    The paper describes the experience acquired in two Spanish nuclear projects in relation to general management, the type of organization selected and the conditions prevailing in Spain. Special attention is given to the relationships established between organization and plant owners, the principal project engineers and the contractor for the nuclear steam producing equipment as well as other contractors and auxiliary engineering groups. A description is given of the legal regime which regulates nuclear activity in Spain, and especially of the system for stimulating national participation in nuclear power plant projects. The procedures for tendering goods and services are explained, as is the system which makes it possible to secure strong participation of Spanish industry in stations based on foreign technology; and some of the problems which this system gives rise to are analysed. An analysis is made of the results obtained in a nuclear plant with two 930 MW units which is ready to go into service and the level of national participation projected for another station of similar capacity due to enter into service in 1983 is discussed. A number of considerations are offered in connection with the Spanish decision to base a large part of the country's future electric power generation on nuclear stations. (author)

  15. Nuclear fuel activity with minor actinides after their useful life in a BWR; Actividad del combustible nuclear con actinidos menores despues de su vida util en un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Martinez C, E.; Ramirez S, J. R.; Alonso V, G., E-mail: eduardo.martinez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    Nuclear fuel used in nuclear power reactors has a life cycle, in which it provides energy, at the end of this cycle is withdrawn from the reactor core. This used fuel is known as spent nuclear fuel, a strong problem with this fuel is that when the fuel was irradiated in a nuclear reactor it leaves with an activity of approximately 1.229 x 10{sup 15} Bq. The aim of the transmutation of actinides from spent nuclear fuel is to reduce the activity of high level waste that must be stored in geological repositories and the lifetime of high level waste; these two achievements would reduce the number of necessary repositories, as well as the duration of storage. The present work is aimed at evaluating the activity of a nuclear fuel in which radioactive actinides could be recycled to remove most of the radioactive material, first establishing a reference of actinides production in the standard nuclear fuel of uranium at end of its burning in a BWR, and a fuel rod design containing 6% of actinides in an uranium matrix from the enrichment tails is proposed, then 4 standard uranium fuel rods are replaced by 4 actinide bars to evaluate the production and transmutation of the same, finally the reduction of actinide activity in the fuel is evaluated. (Author)

  16. Nuclear energy in question

    International Nuclear Information System (INIS)

    Simon, D.N.; Carvalho, J.F. de; Goldemberg, J.; Menezes, L.C.; Rosa, L.P.; Oliveira, R.G. de.

    1981-01-01

    The basic requirements demanded for the physical protection of nuclear operational units, is established. These units can be, production, utilization, processing, reprocessing, handling, transport or storage of materials of interesting to Brazilian Nuclear Program. (E.G.) [pt

  17. Industrial hygiene survey report of Millstone Nuclear Power Station No. 3 construction site (Northeast Utilities Service Co./Stone and Webster Engineering Corp.) Waterford, Connecticut

    International Nuclear Information System (INIS)

    Zaebst, D.D.; Herrick, R.H.

    1985-11-01

    The purpose of the study was to conduct an in-depth industrial hygiene survey to determine exposures of painters to coating components during the construction of a nuclear power plant. The survey was conducted as part of the Industrywide Studies Branch survey of Health Hazards in the Painting Trades

  18. Proceedings of the national symposium on advances in utility systems for industrial and nuclear installations (held at Bombay during January 9-11, 1992)

    International Nuclear Information System (INIS)

    1992-01-01

    The symposium was held when various utility systems, integral and peripheral to industries and organizations undergone a significant advancement in the recent years to cope with the stringent requirements of operating conditions, energy conservation and reliability. The concept of multidisciplinary approach for operating and designing these utility systems have been proved successful to meet demand of ever growing and complex processes. Keeping this in view, the subjects of the symposium were diversified in few major areas like mechanical and electrical systems, control and instrumentation, energy conservation and safety. 73 papers were included in the proceedings

  19. Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia; Dvadeset godina hemije vezane za potrebe i koriscenje nuklearnih reaktora u Institutu za nuklearne nauke 'Boris kidric' i Vinci

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-07-01

    This publication covers nine review papers on the following topics related to the needs and utilization of nuclear reactors in the Boris Kidric Institute of nuclear sciences during previous twenty years: radiochemistry, hot atom chemistry, isotope production, spent nuclear fuel reprocessing, chemistry of transuranium elements; liquid radioactive waste processing, purification of reactor coolant water by inorganic ion exchangers, research related to deuterium concentration processes, and chemical dosimetry at the RA reactor. [Serbo-Croat] Ova publikacija obuhvata devet radova, po sledecim naslovima, a odnose se na potrebe i uslove nuklearnih reaktora u Institutu za nuklearne nauke 'Boris Kidric' tokom prethodnih dvadeset godina: radiohemija, hemija vruceg atoma, proizvodnja radioaktivnih izotopa, prerada isluzenog nuklearnog goriva, hemija transuranskih elemenata, obrada radioaktivnih otpadnih voda, preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca, istrazivanje procesa za koncentrovanje deuterijuma i hemijska dozimetrija reaktora RA.

  20. Broader utilization of programmable automation equipment in French nuclear power plants: Reflections on the choices made by Electricite de France and French designers

    International Nuclear Information System (INIS)

    Baudry, Y.; Varaldi, G.

    1983-01-01

    More than 1000 microprocessors and more than 10,000 data memories in each of the twenty or so 1300 MW units in the French nuclear programme: that was the decision taken by Electricite de France (EDF) in conjunction with the designers in 1974, with the intention of introducing programmable automata on a wide scale in French nuclear power plants. This programme was carried out with the assistance of advanced research services such as the universities, the Commissariat a l'energie atomique (CEA), EDF's design and research service and the designers, most of whom were already EDF suppliers for the 900 MW range. Having used computers for linking sequences (themselves carried out with electromagnetic technology) for its latest natural-uranium gas-cooled graphite-moderated power plants, EDF decided to call a temporary halt, in the case of its 900 MW light-water range, to the use of digital techniques for the control and automation of power plants although it continued to employ such techniques widely in data processing. Thus, the widespread introduction of programmable automata, which was decided upon in 1974/75 at a time when no equivalent existed at the international level, led EDF and French designers to undertake a major development effort in order to meet the requirements - particularly safety and reliability requirements - for such automata to be incorporated into the nuclear field. How does this choice fit in with the logical evolution of the digitalization of French nuclear power plants. What problems has it caused for EDF and French industry. How have these problems been tackled. How have they been overcome. These are the questions dealt with in this paper. (author)

  1. Use of the Modified Light Duty Utility Arm to Perform Nuclear Waste Cleanup of Underground Waste Storage Tanks at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Blank, J.A.; Burks, B.L.; DePew, R.E.; Falter, D.D.; Glassell, R.L.; Glover, W.H.; Killough, S.M.; Lloyd, P.D.; Love, L.J.; Randolph, J.D.; Van Hoesen, S.D.; Vesco, D.P.

    1999-01-01

    The Modified Light Duty Utility Arm (MLDUA) is a selectable seven or eight degree-of-freedom robot arm with a 16.5 ft (5.03 m) reach and a payload capacity of 200 lb. (90.72 kg). The utility arm is controlled in either joystick-based telerobotic mode or auto sequence robotics mode. The MLDUA deployment system deploys the utility arm vertically into underground radioactive waste storage tanks located at Oak Ridge National Laboratory. These tanks are constructed of gunite material and consist of two 25 ft (7.62 m) diameter tanks in the North Tank Farm and six 50 ft (15.24 m) diameter tanks in the South Tank Farm. After deployment inside a tank, the utility arm reaches and grasps the confined sluicing end effecter (CSEE) which is attached to the hose management arm (HMA). The utility arm positions the CSEE within the tank to allow the HMA to sluice the tank's liquid and solid waste from the tank. The MLDUA is used to deploy the characterization end effecter (CEE) and gunite scarifying end effecter (GSEE) into the tank. The CEE is used to survey the tank wall's radiation levels and the physical condition of the walls. The GSEE is used to scarify the tank walls with high-pressure water to remove the wall scale buildup and a thin layer of gunite which reduces the radioactive contamination that is embedded into the gunite walls. The MLDUA is also used to support waste sampling and wall core-sampling operations. Other tools that have been developed for use by the MLDUA include a pipe-plugging end effecter, pipe-cutting end effecter, and pipe-cleaning end effecter. Washington University developed advance robotics path control algorithms for use in the tanks. The MLDUA was first deployed in June 1997 and has operated continuously since then. Operational experience in the first four tanks remediated is presented in this paper

  2. Mox fuel utilization in ATR

    OpenAIRE

    下村 和生; 川太 徳夫

    1987-01-01

    ATR, a heavy-water moderated boiling-light-water cooled reactor developed in Japan, is a unique reactor with out-standing flexibility regarding nuclear fuel utilization, because it has superior properties concerning the utilization of plutonium, recovered uranium and depleted uranium. The development of this type of reactor is expected to contribute both to the stable supply of energy and to the establishment of plutonium utilization in Japan. Much effort has been and will be made on the deve...

  3. A utility perspective on BRC

    International Nuclear Information System (INIS)

    Farrell, B.

    1988-01-01

    The author is program manager for low-level radioactive waste (LLW) for the Utility Nuclear Waste Management Group (UNWMG), an activity funded by 45 utilities with nuclear power programs. The UNWMG represents the utility industry on high-level and low-level radioactive waste issues in legislative, regulatory, and technical proceedings, and therefore has a strong interest in the progress of below-regulatory-concern (BRC) regulations. The author addresses waste disposal volumes prior to discussing recent developments and status of BRC regulations

  4. Nuclear energy

    International Nuclear Information System (INIS)

    Luxo, Armand.

    1977-01-01

    The reasons and conditions of utilizing nuclear power in developing countries are examined jointly with the present status and future uses already evaluated by some organizations. Some consequences are deduced in the human, financial scientific and technological fields, with provisional suggestions for preparing the nuclear industry development in these countries. As a conclusion trends are given to show how the industrialized countries having gained a long scientific and technological experience in nuclear energy can afford their assistance in this field, to developing countries [fr

  5. Nuclear chemical engineering

    International Nuclear Information System (INIS)

    Lee, Geon Jae; Shin, Young Jun

    1989-08-01

    The contents of this book are introduction of chemical engineering and related chemistry on an atomic reactor, foundation of the chemistry nuclear chemical engineering, theory on nuclear engineering, the cycle of uranium and nuclear fuel, a product of nuclear division, nuclear reprocessing, management of spent fuel separation of radioisotope, materials of an atomic reactor, technology and chemistry related water in atomic reactors and utilization of radioisotope and radiation. This book has the exercises and reference books for the each chapter.

  6. Reliability analysis of safety systems of nuclear power plant and utility experience with reliability safeguarding of systems during specified normal operation

    International Nuclear Information System (INIS)

    Balfanz, H.P.

    1989-01-01

    The paper gives an outline of the methods applied for reliability analysis of safety systems in nuclear power plant. The main tasks are to check the system design for detection of weak points, and to find possibilities of optimizing the strategies for inspection, inspection intervals, maintenance periods. Reliability safeguarding measures include the determination and verification of the broundary conditions of the analysis with regard to the reliability parameters and maintenance parameters used in the analysis, and the analysis of data feedback reflecting the plant response during operation. (orig.) [de

  7. Constitutional questions concerning the termination of nuclear energy utilization. The 13th law on the amendment of the atomic law in the frame of basic rights; Verfassungsfragen der Beendigung der Nutzung der Kernenergie. Das 13. Gesetz zur Aenderung des Atomgesetzes im Lichte der Grundrechte

    Energy Technology Data Exchange (ETDEWEB)

    Wieland, Joachim [Deutsche Univ. fuer Verwaltungswissenschaften, Speyer (Germany). Lehrstuhl fuer oeffentliches Recht, Finanz- und Steuerrecht

    2013-06-14

    The nuclear power phaseout in consequence of the nuclear disaster in Fukushima destroyed the expectation of high profits for the NPP owners based on the enacted lifetime extension. Neither professional freedom, nor the principle of property conservation, nor the rule of equality is violated by the termination of nuclear power utilization. The legislative authority was permitted to reverse the decision on the nuclear power utilization towards phaseout. The legislator could invoke its dynamic constitutional obligation for protection of life and physical integrity of the society. The legislator allows the operation of nuclear power plants only if according to the status of science and technology failures that could endanger life and health can practically be excluded. In consequence of the catastrophic accident in Fukushima hazards due to targeted airplane crashes could not be ruled out anymore.

  8. Nuclear economics: Issues and facts

    International Nuclear Information System (INIS)

    Hudson, C.R.

    1993-01-01

    Nuclear economics has become on the more prominent topics related to nuclear power. Beyond the subjects of nuclear safety and waste disposal, questions and concerns of nuclear power economics have emerged with growing frequency in utility board rooms, in state and federal regulatory proceedings, and in the media. What has caused nuclear power economics to become such a popular topic? This paper addresses issues and facts related to historical nuclear plant costs, new nuclear plant projections, and warning signals for future plants

  9. Phosphorus nuclear magnetic resonance imaging in solid bone

    International Nuclear Information System (INIS)

    Li, Limin.

    1990-01-01

    Phosphorus ( 31 P) nuclear magnetic resonance (NMR) double-pulse transient experiments of solid bone have shown that the spins dephased by the dipolar spin-spin interactions can be refocused with a 90 degree-β pulse sequence so that an echo is observable at some time following the second pulse. The decay time constant of the maximum echo amplitude is larger than that of the free induction decay (FID) signal from a single 90 degree pulse. Depending on the nutation angle of the second pulse, the former decay time constant is about three-five times as long as the latter one. The dipolar-echo properties of the bone may be relevant with the interpair dipolar interactions. The experiments have also show that, in general, the time for the transient signal from the double pulses to reach the maximum amplitude is not equal to the pulse separation. This can be attributed to the effect of the heteronuclear dipolar interactions. In addition, it is found experimentally that refocused gradients applied only in a time interval of the formation of an echo have the capability of phase-encoding spatial information. Based on this, a new imaging method was proposed. With the method, several 31 P images of the solid bone samples have been obtained. The picture element size is 1-1.5 mm with very good signal-to-noise ratios. The imaging ability of the refocused gradients may be relevant with the inhomogeneous local field produced by the interpair dipolar interactions

  10. Secondary structure analyses of the nuclear rRNA internal transcribed spacers and assessment of its phylogenetic utility across the Brassicaceae (mustards.

    Directory of Open Access Journals (Sweden)

    Patrick P Edger

    Full Text Available The internal transcribed spacers of the nuclear ribosomal RNA gene cluster, termed ITS1 and ITS2, are the most frequently used nuclear markers for phylogenetic analyses across many eukaryotic groups including most plant families. The reasons for the popularity of these markers include: 1. Ease of amplification due to high copy number of the gene clusters, 2. Available cost-effective methods and highly conserved primers, 3. Rapidly evolving markers (i.e. variable between closely related species, and 4. The assumption (and/or treatment that these sequences are non-functional, neutrally evolving phylogenetic markers. Here, our analyses of ITS1 and ITS2 for 50 species suggest that both sequences are instead under selective constraints to preserve proper secondary structure, likely to maintain complete self-splicing functions, and thus are not neutrally-evolving phylogenetic markers. Our results indicate the majority of sequence sites are co-evolving with other positions to form proper secondary structure, which has implications for phylogenetic inference. We also found that the lowest energy state and total number of possible alternate secondary structures are highly significantly different between ITS regions and random sequences with an identical overall length and Guanine-Cytosine (GC content. Lastly, we review recent evidence highlighting some additional problematic issues with using these regions as the sole markers for phylogenetic studies, and thus strongly recommend additional markers and cost-effective approaches for future studies to estimate phylogenetic relationships.

  11. Prospects for the utilization of small nuclear plants for civil ships, floating heat and power stations and power seawater desalination complexes

    International Nuclear Information System (INIS)

    Polunichev, V.I.

    2000-01-01

    Small power nuclear reactor plants developed by OKB Mechanical Engineering are widely used as propulsion plants in various civil ships. Russia is the sole country in the world that possesses a powerful icebreaker and transport fleet which offers effective solution for vital socio-economic tasks of Russia's northern regions by maintaining a year-round navigation along the Arctic sea route. In the future, intensification of freighting volumes is expected in Arctic seas and at estuaries of northern rivers. Therefore, further replenishment of nuclear-powered fleet is needed by new generation ice-breakers equipped with advanced reactor plants. Adopted progressive design and technology solutions, reliable equipment and safety systems being continuously perfected on the basis of multi year operation experience feedback, addressing updated safety codes and achievement of science and technology, allow the advanced propulsion reactor plants of this type to be recommended as energy sources for floating heat and power co-generation stations and power-seawater desalination complexes. (author)

  12. Utility of combining morphological characters, nuclear and mitochondrial genes: An attempt to resolve the conflicts of species identification for ciliated protists.

    Science.gov (United States)

    Zhao, Yan; Yi, Zhenzhen; Gentekaki, Eleni; Zhan, Aibin; Al-Farraj, Saleh A; Song, Weibo

    2016-01-01

    Ciliates comprise a highly diverse protozoan lineage inhabiting all biotopes and playing crucial roles in regulating microbial food webs. Nevertheless, subtle morphological differences and tiny sizes hinder proper species identification for many ciliates. Here, we use the species-rich taxon Frontonia and employ both nuclear and mitochondrial loci. We attempt to assess the level of genetic diversity and evaluate the potential of each marker in delineating species of Frontonia. Morphological features and ecological characteristics are also integrated into genetic results, in an attempt to resolve conflicts of species identification based on morphological and molecular methods. Our studies reveal: (1) the mitochondrial cox1 gene, nuclear ITS1 and ITS2 as well as the hypervariable D2 region of LSU rDNA are promising candidates for species delineation; (2) the cox1 gene provides the best resolution for analyses below the species level; (3) the V2 and V4 hypervariable regions of SSU rDNA, and D1 of LSU rDNA as well as the 5.8S rDNA gene do not show distinct barcoding gap due to overlap between intra- and inter-specific genetic divergences; (4) morphological character-based analysis shows promise for delimitation of Frontonia species; and (5) all gene markers and character-based analyses demonstrate that the genus Frontonia consists of three groups and monophyly of the genus Frontonia is questionable. Copyright © 2015 Elsevier Inc. All rights reserved.

  13. Utility of four public-policy models as applied to the case study of nuclear materials transportation through the Lehigh Valley

    International Nuclear Information System (INIS)

    Zurat, G.J.

    1982-01-01

    This dissertation assesses four public-policy models by utilizing the case-study approach and personal interviews with the major participants in the public-policy process of Northampton County, Pennsylvania. Northampton County is part of the metropolitan region encompassing Lehigh and Northampton Counties, PA. It is known as the Lehigh Valley which is situated in eastern Pennsylvania. The hypotheses tested in this dissertation are: (1) individual participants have articulated policy models as their frame of reference which guides them in understanding the public policy process, and (2) there is no one best policy model to explain the public-policy process, but the combination of various policy models may improve the policy analysts' understanding of public policy. Results indicate that the major participants have articulated policy models as their frame of reference, but a polarized view of policy models exists for the participants. The second hypothesis was only partially confirmed since the combination of one or more models did not resolve the group/elite policy dilemma of the practitioners. By utilizing stratification theory in the analysis, the group versus elite conflict is clarified and the policy formation phase of the public policy process is understood with respect to the Northamton County Council

  14. The utilization of geochemical parameters for the environmental monitoring of the Nuclear Power Center of Angra I, Ribeira Bay, Rio de Janeiro, Brazil

    International Nuclear Information System (INIS)

    Bidone, E.D.; Carmo Lima, S. do.

    1984-01-01

    In order that a geochemical balance be as complete as possible and thus, reach predictive values for toxic chemical dispersion, an understanding of the hydrological, sedimentological and geological contexts is fundamental. The dispersion of a polluent (in this case radionuclides) is dependent, in part, on its chemical properties and its interaction by sorption and desorption from solid particles (in particular, sediments). This interaction needs to be incorporated in dispersion models and can influence the passage of a pollutant along the food chain. In the case of Ribeira Bay, near the nuclear power center of Angra I, it was observed, through the analysis of sedimentological and geochemical parameters (TOC, TSS, chemical and mineralogical compositions, and granularity): an increase in absorption capacity of surface sediments owing to a homogeneous grain size distribution and a varying clay composition; a possibility of remobilization and transfer of particulate material to areas outside the bay. (Author) [pt

  15. Estimating Utility

    DEFF Research Database (Denmark)

    Arndt, Channing; Simler, Kenneth R.

    2010-01-01

    A fundamental premise of absolute poverty lines is that they represent the same level of utility through time and space. Disturbingly, a series of recent studies in middle- and low-income economies show that even carefully derived poverty lines rarely satisfy this premise. This article proposes a......, with the current approach tending to systematically overestimate (underestimate) poverty in urban (rural) zones.......A fundamental premise of absolute poverty lines is that they represent the same level of utility through time and space. Disturbingly, a series of recent studies in middle- and low-income economies show that even carefully derived poverty lines rarely satisfy this premise. This article proposes...... an information-theoretic approach to estimating cost-of-basic-needs (CBN) poverty lines that are utility consistent. Applications to date illustrate that utility-consistent poverty measurements derived from the proposed approach and those derived from current CBN best practices often differ substantially...

  16. Utility planning for decommissioning

    International Nuclear Information System (INIS)

    Williams, D.H.

    1982-01-01

    Though the biggest impact on a utility of nuclear power plant decommissioning may occur many years from now, procrastination of efforts to be prepared for that time is unwarranted. Foresight put into action through planning can significantly affect that impact. Financial planning can assure the recovery of decommissioning costs in a manner equitable to customers. Decision-making planning can minimize adverse affects of current decisions on later decommissioning impacts and prepare a utility to be equipped to make later decommissioning decisions. Technological knowledge base planning can support all other planning aspects for decommissioning and prepare a utility for decommissioning decisions. Informed project planning can ward off potentially significant pitfalls during decommissioning and optimize the effectiveness of the actual decommissioning efforts

  17. Nuclear technologies

    International Nuclear Information System (INIS)

    Toyama, Makoto; Hamasaki, Manabu; Kobayashi, Masahiko; Hoshide, Akihiko; Katayama, Kimio; Nozawa, H.; Karigome, Satoshi

    2010-01-01

    In recent days, energy security is becoming a major global concern and it has been recognized that a major reduction in greenhouse-gas emissions is required to combat climate change. Considerable expansion and new introduction of nuclear power generation are currently being planned and considered for the further in various parts of the world. Nuclear technologies of the latest 10 years in Japan were reviewed with their characteristics, advancement and future perspective. Steady efforts have been made to construct new nuclear power stations with computer-aided engineering system and modular and prefabricated structures, extend the interval of periodic inspections under the new inspection system that should improve both safety and reliability, implement advanced measures against aging and develop the next-generation light water reactors including a medium small reactor. Export of nuclear power plants has been promoted with international business alliance or cooperation. Activities to close nuclear fuel cycle to ensure sustainable nuclear energy utilization have been promoted. Decommissioning technologies for Tokai power station have been developed and accumulated know-how will be utilized in light water reactors. (T. Tanaka)

  18. Nuclear knowledge management

    International Nuclear Information System (INIS)

    2007-01-01

    The management of nuclear knowledge has emerged as a growing challenge in recent years. The need to preserve and transfer nuclear knowledge is compounded by recent trends such as ageing of the nuclear workforce, declining student numbers in nuclear-related fields, and the threat of losing accumulated nuclear knowledge. Addressing these challenges, the IAEA promotes a 'knowledge management culture' through: - Providing guidance for policy formulation and implementation of nuclear knowledge management; - Strengthening the contribution of nuclear knowledge in solving development problems, based on needs and priorities of Member States; - Pooling, analysing and sharing nuclear information to facilitate knowledge creation and its utilization; - Implementing effective knowledge management systems; - Preserving and maintaining nuclear knowledge; - Securing sustainable human resources for the nuclear sector; and - Enhancing nuclear education and training

  19. Nuclear energy and environment

    International Nuclear Information System (INIS)

    Alves, R.N.

    1987-01-01

    A general view about the use of energy for brazilian development is presented. The international situation of the nuclear field and the pacific utilization of nuclear energy in Brazil are commented. The safety concepts used for reactor and nuclear facilities licensing, the environmental monitoring program and radiation protection program used in Brazil are described. (E.G.) [pt

  20. Siting of nuclear power stations and the scope of preoperational investigations with special considerations of demographic aspects and the economic utilization of the neighbouring areas

    International Nuclear Information System (INIS)

    Bijak, J.

    1976-01-01

    The studies are presented on the location of atomic power stations in Poland made so far. The methods used in the studies are described which were done in two stages: preliminary location studies on the macroregional scale, and location studies on one or more of the chosen locations. Part one deals with general conditions which have to be met for location of atomic power stations and with preliminary assumptions accepted by GBS i PE ''Energoprojekt'' for location studies. Regulations and recommendations for establishing sites for atomic power stations are also given. Special location conditions are dealt with more extensively, the enviromental hazards and the need for their studies being particularly emphasized. Part two describes the scope of studies made prior to and after the time location investigations. Demographic studies and the economic utilization of the neighbouring areas are presented in more detail. (author)

  1. Siting of nuclear power stations and the scope of preoperational investigations with special considerations of demographic aspects and the economic utilization of the neighbouring areas. [Poland

    Energy Technology Data Exchange (ETDEWEB)

    Bijak, J [Biuro Studiow i Projektow ' Energoprojekt' , Warsaw (Poland)

    1976-01-01

    Studies are presented on the location of atomic power stations in Poland. The methods used in the studies are described which were done in two stages: preliminary location studies on the macroregional scale, and location studies on one or more of the chosen locations. Part one deals with general conditions which have to be met for location of atomic power stations and with preliminary assumptions accepted by GBS i PE ''Energoprojekt'' for location studies. Regulations and recommendations for establishing sites for atomic power stations are also given. Special location conditions are dealt with more extensively, the enviromental hazards and the need for their studies being particularly emphasized. Part two describes the scope of studies made prior to and after the time location investigations. Demographic studies and the economic utilization of the neighbouring areas are presented in more detail.

  2. Absolute nuclear material assay

    Science.gov (United States)

    Prasad, Manoj K [Pleasanton, CA; Snyderman, Neal J [Berkeley, CA; Rowland, Mark S [Alamo, CA

    2010-07-13

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  3. Obtaining the neutron time-of-flight instrument response function for a single D-T neutron utilizing n-alpha coincidence from the d(t, α) n nuclear reaction

    Science.gov (United States)

    Styron, Jedediah; Ruiz, Carlos; Hahn, Kelly; Cooper, Gary; Chandler, Gordon; Jones, Brent; McWatters, Bruce; Smith, Jenny; Vaughan, Jeremy

    2017-10-01

    A measured neutron time-of-flight (nTOF) signal is a convolution of the neutron reaction history and the instrument response function (IRF). For this work, the IRF was obtained by measuring single, D-T neutron events by utilizing n-alpha coincidence. The d(t, α) n nuclear reaction was produced at Sandia National Laboratories' Ion Beam Laboratory using a 300-keV Cockroft-Walton generator to accelerate a 2- μA beam, of 175-keV D + ions, into a stationary, 2.6- μm, ErT2 target. Comparison of these results to those obtained using cosmic-rays and photons will be discussed. Sandia National Laboratories.

  4. Impact of the legislation on electric utilities

    International Nuclear Information System (INIS)

    De Long, M.

    1982-01-01

    The possible impact of Federal nuclear waste legislation on electric utilities is discussed. The proposed legislation will set forth a well defined program enabling utilities with nuclear plants to make long term plans under a statutory mandate committed to an available technology and implementation timetable. The legislation includes the necessary specificity for the utility companies to fulfill their responsibilities in describing their waste disposal plans to their customers, the concerned public, and state and local legislators

  5. National phantoms bank for the service of nuclear medicine in Cuba. Utility for the quality control of the instrumentation; Banco de fantomas nacional para los servicios de medicina nuclear en Cuba. Utilidad para el control de calidad de la instrumentacion

    Energy Technology Data Exchange (ETDEWEB)

    Varela C, C.; Diaz B, M. [CCEEM, Calle 4 No. 455 (altos) e/19 y 21, Vedado, Ciudad Habana (Cuba); Lopez B, G.M. [CPHR, Calle 20 No. 4113 e/41 y 47, Playa Ciudad Habana (Cuba)]. e-mail: consuelo.varela@infomed.sld.cu

    2006-07-01

    Although, most of the applications in Nuclear Medicine have diagnostic ends, its going enlarging considerably the therapeutic applications. So that the diagnostic accuracy or the therapy effectiveness have not been affected, it becomes indispensable the quality control of the instrumentation, independently of its technological complexity and/or its exploitation period. Before the real lack of phantoms in the institutions, it was created a bank that puts to disposition of all the institutions, the existent phantoms in the country, and those that are going acquired, centralized by the State Control of Medical Equipment Center (CCEEM) and with Web access in its place www.eqmed.sld.cu. Having like base the elaboration of the National Protocol for the Quality Control of the Instrumentation in Nuclear Medicine that keeps in mind the international normative and the own existent conditions, were dictated and established two national regulations and its are being carried out the first audits to the instrumentation quality. These have evidenced the partial realization of the established quality controls in the services, the necessity to make aware as for the fulfillment of the criteria and quality concepts for the instrumentation, as well as the necessity to increase the phantoms number to the bank to guarantee the fulfillment of the Quality Control Programs. (Author)

  6. Utilization of special computerized tomography and nuclear medicine techniques for quality control and for the optimization of combined precision chemotherapy and precision radiation therapy

    International Nuclear Information System (INIS)

    Wiley, A.L. Jr.; Wirtanen, G.W.; Chien, I.-C.

    1984-01-01

    A combination of precision (selective, intra-arterial) chemotherapy and precision radiotherapy can be used for advanced pancreatic, biliary tract, and sarcomatous malignancies. There were some remarkable responses, but also a few poor responses and even some morbidity. Accordingly, methods are developed of pre-selecting those patients whose tumors are likely to respond to such therapy, as well as methods for improving the therapeutic ratio by the rational optimization of combined therapy. Specifically, clinical tumor blood flow characteristics (monitored with nuclear medicine techniques) may provide useful criteria for such selection. The authors also evaluate qualitatively the drug distribution or exposure space with specialized color-coded computerized tomography images, which demonstrate spatially dependent enhancement of intra-arterial contrast in tumor and in adjacent normal tissues. Such clinical data can improve the quality control aspects of intra-arterial chemotherapy administration, as well as the possibility of achievement of a significant therapeutic ratio by the integration of precision chemotherapy and precision radiation therapy. (Auth.)

  7. An experimental study on a training support system utilizing trainee's eye gaze point and think aloud protocol for diagnosing nuclear power plant anomalies

    International Nuclear Information System (INIS)

    Ozawa, Takahisa; Samejima, Ryouta; Shimoda, Hiroshi; Yoshikawa, Hidekazu

    2003-01-01

    An experimental system has been developed for aiming at supporting the simulator training of diagnosis nuclear power plant anomaly, where an expert provides the instructions to a trainee by his/her own educational and experienced point of view. This system has several characteristics as follows: (1) the expert can provide the instruction through the local area network or the Internet, (2) the training task is the detection of the primary cause of plant anomaly, which is not including the plant operation but requires only thinking, and (3) the system can automatically detects the trainee's view-point and think aloud protocols and provide these two types of information to the expert in real time for supporting his/her instruction. A laboratory experiment using this system was conducted, where an expert, who had really engaged in plant operation as a chief operator, was employed as the instructor for novice students. As the result of analyzing the experimental data, it was found that the two types of information, trainee's viewpoints and his verbal protocols, have some potential of effectiveness for supporting the instructor to estimate the trainees diagnostic thinking process and provide the instruction. (author)

  8. The use of nuclear and related techniques for evaluating the agronomic effectiveness of phosphate fertilizers, in particular rock phosphate, in Venezuela: I. phosphorus uptake, utilization and agronomic effectiveness

    International Nuclear Information System (INIS)

    Casanova, E.; Salas, A.M.; Toro, M.

    2002-01-01

    Field experiments were conducted to evaluate the efficiency of natural and modified rock phosphate using conventional and isotopic techniques in an acid soil from El Pao, Cojedes state, Venezuela, using maize and sorghum with the application of different phosphate fertilizers to measure dry matter production, P accumulated in plant, efficiency parameters using isotopic techniques or yield. Finally, commercial plots were established with the application of soluble P fertilizers and rock phosphate products to validate the results obtained in the field experiments. The results showed highly significant differences between partially acidulated rock phosphate, natural rock phosphate, and the check plot in dry matter production, and P accumulation in plant and grain yield. When the efficiency parameters were evaluated in microplots with 32 P-TSP at 60 days of plant growth, it confirmed results obtained in semi commercial plots where the P in the plant derived from the fertilizer was 46% with partially acidulated rock phosphate (PAR) and 14% with natural Riecito rock phosphate (RR). Utilization coefficients of P by the plants were 34.2 and 8.8% for both treatments, respectively. The Substitution relation parameter showed that just 0.8 kg of P of PAR or 3.1 kg P of RR was required to produce the same yield as 1 kg P of TSP. These results were further validated in 5 ha commercial plots using corn and sorghum. (author)

  9. Nuclear methods in environmental and energy research

    Energy Technology Data Exchange (ETDEWEB)

    Vogt, J. R. [ed.

    1977-01-01

    The topics considered in the seven sessions were nuclear methods in atmospheric research; nuclear and atomic methodology; nuclear methods in tracer applications; energy exploration, production, and utilization; nuclear methods in environmental monitoring; nuclear methods in water research; and nuclear methods in biological research. Individual abstracts were prepared for each paper. (JSR)

  10. U.S. nuclear plant decommissioning funding adequacy - by individual funds, utilities, reactors, and industry-wide - assessed by Monte Carlo and baseline trend methods: 1998, 2000, 2001, and 2004

    International Nuclear Information System (INIS)

    Williams, Daniel G.

    2007-01-01

    This paper assesses, over years 1998, 2000, 2001, and 2004 - using varying sets of assumption values - the adequacy of decommissioning funding (year-end) for United States' nuclear electric power plants. I assess each of the 222 individual trust funds and 99 utility owners (as of August 2003), as well as each of the 122 reactors, and industry-wide. Individual trust fund results are the most important because, in general, dollars may not be transferred from one fund to another to strengthen a less-adequately financed fund. Using stochastic (Monte Carlo) analysis (20,000 iterations) to incorporate risk, or uncertainty, in my simulation modeling, I assess funding adequacy for 2004, but with estimated balances and contributions data for 2004. The paper also assesses the baseline (most likely) trends in funding adequacy, using 'point' estimates for years 1998, 2000, 2001, and stochastic medians for 2004. I compute two measures of funding adequacy relative to two respective benchmark levels: (1) adequacy of 'current year' fund balances; and (2), adequacy of 'recent-year' fund contributions. The former is a more 'looking-backward' measure relative to a benchmark (i.e., current balance embodies all past year contributions and rates of return on fund assets); the latter, more 'looking-forward' relative to a forward benchmark. I use decommissioning fund balances data for 2000 and 1998, as reported by the utilities to the U.S. Nuclear Regulatory Commission (NRC), as well as additional balances, yearly contributions, rates of return, and cost escalation data over 1997-2001 obtained in a 2002 survey of owners by the U.S. Government Accountability Office (GAO). The most fundamental conclusion that one should draw from my simulation modeling results - whether using Monte Carlo or baseline trend analysis - is that these decommissioning adequacy percentages for the 222 funds are extremely variable, although a sizable majority of funds are likely above benchmark. Reduced variability

  11. Multiattribute Utility Theory without Expected Utility Foundations

    NARCIS (Netherlands)

    Stiggelbout, A.M.; Wakker, P.P.

    1995-01-01

    Methods for determining the form of utilities are needed for the implementation of utility theory in specific decisions. An important step forward was achieved when utility theorists characterized useful parametric families of utilities, and simplifying decompositions of multiattribute utilities.

  12. Multiattribute utility theory without expected utility foundations

    NARCIS (Netherlands)

    Wakker, P.P.; Miyamoto, J.

    1996-01-01

    Methods for determining the form of utilities are needed for the implementation of utility theory in specific decisions. An important step forward was achieved when utility theorists characterized useful parametric families of utilities, and simplifying decompositions of multiattribute utilities.

  13. Developing utility emergency preparedness exercises

    International Nuclear Information System (INIS)

    Sjoeblom, K.

    1986-01-01

    Utility emergency preparedness exercises constitute an important link in upgrading the response to nuclear power plant emergencies. Various emergency exercises are arranged annually at the Loviisa nuclear power plant. The on-site simulator is a practical tool in developing suitable accident scenarios and demonstrating them to the site emergency players and spectators. The exercises concentrate on emergency management and radiological activities. It is important to create a high degree of motivation. (author)

  14. Nuclear risk

    International Nuclear Information System (INIS)

    Levenson, M.

    1989-01-01

    The title of our session, Nuclear Risk Versus Other Power Options, is provocative. It is also a title with different meanings to different people. To the utility chief executive officer, nuclear power is a high-risk financial undertaking because of political and economic barriers to cost recovery. To the utility dispatcher, it is a high-risk future power source since plant completion and start-up dates can be delayed for very long times due to uncertain legal and political issues. To the environmentalist, concerned about global effects such as greenhouse and acid rain, nuclear power is a relatively low risk energy source. To the financial people, nuclear power is a cash cow turned sour because of uncertainties as to what new plants will cost and whether they will even be allowed to operate. The statistics on risk are known and the results of probability risk assessment calculations of risks are known. The challenge is not to make nuclear power safer, it is already one of the safest, if not the safest, source of power currently available. The challenge is to find a way to communicate this to the public

  15. The Text of the Agreement between Iraq and the Agency for the Application of Safeguards in connection with the Treaty on the Non-Proliferation of Nuclear Weapons. An Exchange of Letters between the Government of the French Republic and the Government of the Republic of Iraq Supplementary to the Franco-Iraqi Co-Operation Agreement for the Peaceful Utilization of Nuclear Energy Signed on 18 November 1975

    International Nuclear Information System (INIS)

    1979-09-01

    The text of the exchange of letters of 11 September 1976 between the Government of the French Republic and the Government of the Republic of Iraq supplementary to the Franco-Iraqi cooperation agreement for the peaceful utilization of nuclear energy of 18 November 1975 is reproduced in this document for the information of all Members by agreement with the French and Iraqi Governments

  16. The Text of the Agreement between Iraq and the Agency for the Application of Safeguards in connection with the Treaty on the Non-Proliferation of Nuclear Weapons. An Exchange of Letters between the Government of the French Republic and the Government of the Republic of Iraq Supplementary to the Franco-Iraqi Co-Operation Agreement for the Peaceful Utilization of Nuclear Energy Signed on 18 November 1975

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1979-09-15

    The text of the exchange of letters of 11 September 1976 between the Government of the French Republic and the Government of the Republic of Iraq supplementary to the Franco-Iraqi cooperation agreement for the peaceful utilization of nuclear energy of 18 November 1975 is reproduced in this document for the information of all Members by agreement with the French and Iraqi Governments.

  17. Seminar on utilization of nuclear techniques in the agricultural research carried out in FONAIAP. Abstracts and lectures; Seminario sobre utilizacion de tecnicas nucleares en la investigacion agropecuaria realizada en el FONAIAP. Resumenes y ponencias

    Energy Technology Data Exchange (ETDEWEB)

    Romero S, Alfredo [ed.; Bracamonte, Magaly [Fondo Nacional de Investigaciones Agropecuarias (FONAIAP), Centro Nacional de Investigaciones Agropecuarias (CENIAP), Maracay (Venezuela)

    1997-07-01

    The lectures included in this seminar are related to: development and evaluation of prophylactic methods to control the anaplasmosis and babesiosis (babesia bovis) in the livestock; the diagnosis of bovine basesiosis (babesia bovis) by means of the test of ELISA; validation of the kit ELISA (FAO, OIEA, PANAFTOSA) to determine antibodies against the virus of the foot and mouth disease; variability generation in sugar cane for resistance to mosaic viruses and rusts (puccinia melanocephala) by means of the cultivation of explants and irradiated callus; bioavailabilty of deposit phosphates in animal feeding; biological fixation of nitrogen in three tropical feed crops leguminous and its transfer to Brachiaria humidicola in association; unit of stable isotopic N{sup 1}5 analysis; effect of the efficiency of N by use of different forms of fertilizer application in ground, evaluated by means of the isotopic technique and the N absorbed by the cultivation; application of progesterone and testosterone in the diagnose and control of reproduction in crossbreeds animal husbandry; advances in the monitoring of production systems in double purpose cattle raising in the area of Guayabal, Guarico State; aquatic investigations with nuclear energy techniques; development of the Venezuelan Edaphological Bibliographic Database. [Spanish] Las ponencias presentadas en este seminario tratan sobre: desarrollo y evaluacion de metodos profilacticos para controlar la anaplasmosis y babesiosis en el ganado; el diagostico de la babesiosis bovina (babesia bovis) mediante la prueba de ELISA; la validacion del kit de ELISA FAO/OIEA/PANAFTOSA para determinar anticuerpos contra el virus de la fiebre aftosa; generacion de variabilidad en cana de azucar para resistencia a mosaico y roya (puccinia melanocephala) mediante el cultivo de explantes y callos irradiados; biodisponibilidad de fosfatos de yacimientos en la alimentacion animal; fijacion biologica de nitrogeno en tres leguminosas forrajeras

  18. Nuclear awaits 1994

    International Nuclear Information System (INIS)

    Collier, J.G.

    1992-01-01

    When the UK electricity industry was privatised, the Government stated that in 1994 it would undertake a review of the prospects for nuclear power. The future role of nuclear power will be viewed against the improved performance of the nuclear utilities; the success being achieved on the construction of Sizewell B; and the economics taking into account environmental benefits. The chairman of Nuclear Electric reviews the current position of Nuclear Power in Britain and puts the case for nuclear power in the future. (author)

  19. Present market for nuclear energy

    International Nuclear Information System (INIS)

    Marzo, M.A.S.

    1987-01-01

    The present market for nuclear energy is present since nuclear production and electric power generation to the utilization of radioisotopes in medicine and biology. Some data about the main world suppliers to this market are shown. (E.G.) [pt

  20. Energy utilization in Canada

    International Nuclear Information System (INIS)

    Klassen, J.

    1976-04-01

    The situation of the energy supply of Canada is characterized by its geographic location and by the dispersal of the energy consumers over a wide area. At present, the energy supply leaving the successful CANDU nuclear energy programme out of account, is based mainly on crude oil, natural gas, and electricity as well as on coal imported from the USA. The targets of Canadian enery policies and energy research are stated as follows: a) Reducing and optimizing energy consumption, b) introducing district heating, and c) utilizing the extensive local coal deposits. (GG) [de

  1. RA Research nuclear reactor, Part I - RA nuclear reactor operation, maintenance and utilization in 1984; Istrazivacki nuklearni reaktor RA - Deo I - Pogon, odrzavanje i eksploatacija nuklearnog reaktora RA u 1984. godini

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O; Martinc, R; Cupac, S; Sulem, B; Badrljica, R; Majstorovic, D; Sanovic, V [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1984-12-15

    During the 1984 the reactor operation was limited by the temporary operating license issued by the Committee of Serbian ministry for health and social care. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. This temporary license has limited the reactor power to 2 MW from 1981. Operation of the primary cooling system was changed in order to avoid appearance of the previously noticed aluminium oxyhydrate on the surface of the fuel element claddings. The new cooling regime enabled more efficient heavy water purification. Control and maintenance of the reactor instrumentation and tools was done regularly but dependent on the availability of the spare parts. In order to enable future reliable operation of the RA reactor, according to new licensing regulations, during 1984, three major tasks are planned: building of the new emergency system, reconstruction of the existing ventilation system, and renewal of the reactor instrumentation. Financing of the planned activities will be partly covered by the IAEA. this Part I of the report includes 8 Annexes describing in detail the reactor operation, and 6 special papers dealing with the problems of reactor operation and utilization.

  2. Utilization of research reactors

    International Nuclear Information System (INIS)

    1962-01-01

    About 200 research reactors are now in operation in different parts of the world, and at least 70 such facilities, which are in advanced stages of planning and construction, should be critical within the next two or three years. In the process of this development a multitude of problems are being encountered in formulating and carrying out programs for the proper utilization of these facilities, especially in countries which have just begun or are starting their atomic energy work. An opportunity for scientific personnel from different Member States to discuss research reactor problems was given at an international symposium on the Programing and Utilization of Research Reactors organized by the Agency almost immediately after the General Conference session. Two hundred scientists from 35 countries, as well as from the European Nuclear Energy Agency and EURATOM, attended the meeting which was held in Vienna from 16 to 21 October 1961

  3. Phosphorus-31 MRI of bones using quadratic echo line-narrowing

    Science.gov (United States)

    Frey, Merideth; Barrett, Sean; Insogna, Karl; Vanhouten, Joshua

    2012-02-01

    There is a great need to probe the internal composition of bone on the sub-0.1 mm length scale, both to study normal features and to look for signs of disease. Despite the obvious importance of the mineral fraction to the biomechanical properties of skeletal tissue, few non-destructive techniques are available to evaluate changes in its chemical structure and functional microarchitecture on the interior of bones. MRI would be an excellent candidate, but bone is a particularly challenging tissue to study given the relatively low water density and wider linewidths of its solid components. Recent fundamental research in quantum computing gave rise to a new NMR pulse sequence - the quadratic echo - that can be used to narrow the broad NMR spectrum of solids. This offers a new route to do high spatial resolution, 3D ^31P MRI of bone that complements conventional MRI and x-ray based techniques to study bone physiology and structure. We have used our pulse sequence to do 3D ^31P MRI of ex vivo bones with a spatial resolution of (sub-450 μm)^3, limited only by the specifications of a conventional 4 Tesla liquid-state MRI system. We will describe our plans to push this technique towards the factor of 1000 increase in spatial resolution imposed by fundamental limits.

  4. The examination of cardiac metabolism of patients with hypercholesterolemia by phosphorus-31 magnetic resonance spectroscopy

    International Nuclear Information System (INIS)

    Martinek, M.

    2001-07-01

    Objectives: we decided to investigate weather alterations in high energy phosphates occur in the myocardium of persons with hypercholesterolemia. Background: myocardial high energy phosphates have been shown to be reduced in various diseases of the heart such as coronary artery disease, heart failure and dilated cardiomyopathy. The latest studies on hypercholesterolemia show direct effects of high serum cholesterol on heart muscle cells, so do studies on statins. Methods: in the present study 32 male patients (mean age 48) with hypercholesterolemia and 27 male healthy volunteers (mean age 44,5) as age matched controls were included. The patients were divided into a statin-treated (n = 17) and an untreated subgroup (n = 15). Using a 1,5 Tesla whole-body magnetic resonance scanner (Siemens, Germany) phosphor-31 magnetic resonance spectroscopic imaging (31P MRSI) of the heart was performed in all subjects. The 31P MRSI slab (slab thickness = 40 mm, field of view = 320 mm, matrix 32 x 32, TR = 323 ms, TE 3 ms) contained the left anterior ventricular wall (region of interest = 32 ml). The measurement was triggered on electrocardiography. The ratios of phosphocreatinine (PCr) to β-adenosine-triphosphate (β-ATP) were calculated. Results: the myocardium of untreated patients with hypercholesterolemia shows significantly decreased ratios of PCr/β-ATP compared with patients treated with statins (2,09 vs. 2,45). When comparing the untreated group with healthy persons there was a trend to significance for a difference of the groups (2,09 vs. 2,34). Conclusion: with this study we demonstrate the first time alterations of high energy phosphates in the myocardium of persons with hypercholesterolemia and the beneficial effects of statins on these parameters. (author)

  5. Nuclear watershed

    International Nuclear Information System (INIS)

    Makovich, L.; Parish, T.

    1984-01-01

    In 1979 the accident at Three Mile Island brought nuclear power to the forefront of national attention. Over the last five years there have been no new orders for nuclear plants, construction costs and lead times have increased drastically, and numerous plants have been cancelled. In the coming years many new plants will come on line, and the first round of nuclear plant retirements will begin. Thus, the new set of issues faced by utilities are whether to complete plants currently under construction, how to recover the cost of abandoned plants, how to handle the potential rate shock of bringing costly plants into rate base, and how to accomplish decommissioning and retirement of nuclear plants. This paper presents and analyzes these issues. First, the history of the nuclear electric generation industry is reviewed. Next a case study illustrating the cost momentum built into nuclear power plant construction is presented. The issues involved in plant cancellation are discussed. Finally, a case study involving rate phase-in strategies is analyzed. 1 reference, 7 figures

  6. Thorium utilization

    Energy Technology Data Exchange (ETDEWEB)

    Trauger, D B [Oak Ridge National Lab., TN (USA)

    1978-01-01

    Some of the factors that provide incentive for the utilization of thorium in specific reactor types are explored and the constraints that stand in the way are pointed out. The properties of thorium and derived fuels are discussed, and test and reactor operating experience is reviewed. In addition, symbiotic systems of breeder and converter reactor are suggested as being particularly attractive systems for energy production. Throughout the discussion, the High-Temperature Gas-Cooled Reactor and Molten Salt Reactor are treated in some detail because they have been developed primarily for use with thorium fuel cycles.

  7. Thorium utilization in power reactors

    International Nuclear Information System (INIS)

    Saraceno; Marcos.

    1978-10-01

    In this work the recent (prior to Aug, 1976) literature on thorium utilization is reviewed briefly and the available information is updated. After reviewing the nuclear properties relevant to the thorium fuel cycle we describe briefly the reactor systems that have been proposed using thorium as a fertile material. (author) [es

  8. Waste heat utilization in agriculture

    International Nuclear Information System (INIS)

    Horacek, P.

    1983-01-01

    The Proceedings contain 17 papers presented at meetings of the Working Group for Waste Heat Utilization of the Committee of the European Society of Nuclear Methods in Agriculture of which 7 fall under the INIS scope. The working group met in May 1980 in Brno, Czechoslovakia, in October 1981 in Aberdeen, Scotland and in September 1982 in Brno. (Z.M.)

  9. Multiattribute Utility Theory without Expected Utility Foundations

    NARCIS (Netherlands)

    J. Miyamoto (John); P.P. Wakker (Peter)

    1996-01-01

    textabstractMethods for determining the form of utilities are needed for the implementation of utility theory in specific decisions. An important step forward was achieved when utility theorists characterized useful parametric families of utilities and simplifying decompositions of multiattribute

  10. The text of the Agreement of 9 June 1982 between the Federal Republic of Germany, Spain and the Agency for the application of safeguards in connection with the Agreement between the Governments on co-operation in the field of the utilization of nuclear energy for peaceful purposes of 5 December 1978

    International Nuclear Information System (INIS)

    1983-07-01

    The full text of the agreement of 9 June 1982 between the Federal Republic of Germany, Spain and the Agency for the application of safeguards in connection with the agreement between the Governments in co-operation in the field of the utilization of nuclear energy for peaceful purposes of 5 December 1978 is presented

  11. Economic Analysis of Nuclear Energy

    International Nuclear Information System (INIS)

    Lee, Man Ki; Moon, K. H.; Kim, S. S.; Lim, C. Y.; Oh, K. B.

    2006-12-01

    It has been well recognized that securing economic viabilities along with technologies are very important elements in the successful implementation of nuclear R and D projects. The objective of the Project is to help nuclear energy to be utilized in an efficient way by analyzing major issues related with nuclear economics. The study covers following subjects: the role of nuclear in the future electric supply system, economic analysis of nuclear R and D project, contribution to the regional economy from nuclear power. In addition, the study introduces the international cooperation in the methodological area of efficient use of nuclear energy by surveying the international activities related with nuclear economics

  12. Economic Analysis of Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Man Ki; Moon, K. H.; Kim, S. S.; Lim, C. Y.; Oh, K. B

    2006-12-15

    It has been well recognized that securing economic viabilities along with technologies are very important elements in the successful implementation of nuclear R and D projects. The objective of the Project is to help nuclear energy to be utilized in an efficient way by analyzing major issues related with nuclear economics. The study covers following subjects: the role of nuclear in the future electric supply system, economic analysis of nuclear R and D project, contribution to the regional economy from nuclear power. In addition, the study introduces the international cooperation in the methodological area of efficient use of nuclear energy by surveying the international activities related with nuclear economics.

  13. Guidelines and workbook for of organization and administration of utilities seeking operating license for a nuclear power plant. Workbook for assessment of organization and management. Volume, 2, Revision 1

    International Nuclear Information System (INIS)

    Thurber, J.A.; Olson, J.; Osborn, R.N.; Sommers, P.; Widrig, R.D.

    1986-09-01

    This report is a partial response to the requirements of Item I.B.1.1 of the ''NRC Action Plan Developed as a Result of the TMI-2 Accident,'' NUREG-0660, and is designed to serve as a basis for replacing the earlier NUREG-0731, ''Guidelines for Utility Management Structure and Technical Resources.'' The Guidelines are intended to provide guidance to the user in preparing a written plan for a proposed nuclear organization and administration. The purpose of the Workbook is to guide the NRC reviewer through a systematic review and assessment of a proposed organization and administration. It is the NRC's intention to incorporate these Guidelines and Workbook into a future revision of the Standard Review Plan (SRP), NUREG-0800. However, at this time the report is being published so that the material may be used on a voluntary basis by industry to systematically prepare or evaluate their organization or administration plans. Use of the report by the NRC would not occur until after it has been incorporated in the SRP

  14. The NRC and utility finances

    International Nuclear Information System (INIS)

    Byus, L.C.

    1992-01-01

    In a speech before the National Association of Regulatory Utility Commissioners in November 1991, Nuclear Regulatory Commission Chairman Ivan Selin presented what he called an open-quotes expansion of the concept of safety beyond our previous narrow bounds.close quotes He went on to explain, open-quotes To be seen as successful and safe operators of nuclear facilities, utilities must have safe and predictable cash flows.close quotes While there is little disagreement that the concepts of successful plant operations and financial strength go hand in hand, the relationship between the two is not clear. Which came first, successful operation of generating plants or financial strength? Selin's views on NRC involvement in financial aspects of utility operation in the United States are sure to stimulate debate on the issue

  15. Calculating utility prudency issue costs

    International Nuclear Information System (INIS)

    Nielsen, K.R.

    1985-01-01

    The nuclear industry, particularly utilities and their construction, engineering and vendor agents, is faced with a surging increase in prudency management audits. What started as primarily a nuclear project-oriented requirement has spread to encompass most significant utility capital construction projects. Such audits are often a precedent condition to commencement of rate hearings. The cost engineer, a primary major capital construction project participant, is required to develop or critique ''prudency issue'' costs as part of such audits. Although utility costs in the broadest sense are potentially at issue, this paper concentrates on the typical project/construction management costs. The costs of design, procurement and construction are all subject to the calculation process

  16. Nuclear power generation and nuclear nonproliferation

    International Nuclear Information System (INIS)

    Walske, C.

    1978-01-01

    In the future outlook around year 2000 of nuclear power, thought must be given to fuel reprocessing and plutonium utilization. The adverse utilization of plutonium may be prevented by the means balanced with its economical value. As the method of less cost with lower effect of nonproliferation, combination of fuel reprocessing and fuel fabrication facilities and mixed plutonium/uranium processing are possible. As the method of more cost with higher effect of nonproliferation the maintenance of high radioactivity and inaccessibility of plutonium is conceivable. As for the agreeable methods in 2000, seven principles may be mentioned, such as the dependence upon the agreements among major nations and upon nuclear exporting countries. These are still inadequate, however. What is important is to provide with the sufficient safeguards to countries concerned to negate the need for nuclear weapons. Efforts are then necessary for leading nuclear countries to extend aids to other nuclear-oriented countries. (Mori, K.)

  17. Nuclear law - Nuclear safety

    International Nuclear Information System (INIS)

    Pontier, Jean-Marie; Roux, Emmanuel; Leger, Marc; Deguergue, Maryse; Vallar, Christian; Pissaloux, Jean-Luc; Bernie-Boissard, Catherine; Thireau, Veronique; Takahashi, Nobuyuki; Spencer, Mary; Zhang, Li; Park, Kyun Sung; Artus, J.C.

    2012-01-01

    This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

  18. Nuclear techniques in industry

    International Nuclear Information System (INIS)

    Hammad, F.H.

    1994-01-01

    Nuclear techniques are utilized in almost every industry. The discussion in this paper includes discussions on tracer methods and uses nucleonic control systems technology; non-destructive testing techniques and radiation technology. 1 fig., 2 tabs

  19. Fuel manufacturing and utilization

    International Nuclear Information System (INIS)

    2005-01-01

    The efficient utilisation of nuclear fuel requires manufacturing facilities capable of making advanced fuel types, with appropriate quality control. Once made, the use of such fuels requires a proper understanding of their behaviour in the reactor environment, so that safe operation for the design life can be achieved. The International Atomic Energy Agency supports Member States to improve in-pile fuel performance and management of materials; and to develop advanced fuel technologies for ensuring reliability and economic efficiency of the nuclear fuel cycle. It provides assistance to Member States to support fuel-manufacturing capability, including quality assurance techniques, optimization of manufacturing parameters and radiation protection. The IAEA supports the development fuel modelling expertise in Member States, covering both normal operation and postulated and severe accident conditions. It provides information and support for the operation of Nuclear Power Plant to ensure that the environment and water chemistry is appropriate for fuel operation. The IAEA supports fuel failure investigations, including equipment for failed fuel detection and for post-irradiation examination and inspection, as well as fuel repair, it provides information and support research into the basic properties of fuel materials, including UO 2 , MOX and zirconium alloys. It further offers guidance on the relationship with back-end requirement (interim storage, transport, reprocessing, disposal), fuel utilization and management, MOX fuels, alternative fuels and advanced fuel technology

  20. Industry activities to resolve utility procurement issues

    International Nuclear Information System (INIS)

    Rosch, F.

    1993-01-01

    There are several industry organizations which are active in assisting the utilities in their equipment procurement enhancement. They include the Nuclear Management Resources Council (NUMARC), the Electric Power Research Institute (EPRI), and the Nuclear Procurement Issues Committee (NUPIC). The products include the NUMARC Procurement Initiatives, EPRI procurement related guidelines and databases, and NUPIC joint audits and commercial grade surveys. The industry procurement activities and products are reviewed, and their use by utilities to enhance their procurement process is related. 1 fig