Characterization of DNA substrate specificities of apurinic/apyrimidinic endonucleases from Mycobacterium tuberculosis.

Science.gov (United States)

Abeldenov, Sailau; Talhaoui, Ibtissam; Zharkov, Dmitry O; Ishchenko, Alexander A; Ramanculov, Erlan; Saparbaev, Murat; Khassenov, Bekbolat

2015-09-01

Apurinic/apyrimidinic (AP) endonucleases are key enzymes involved in the repair of abasic sites and DNA strand breaks. Pathogenic bacteria Mycobacterium tuberculosis contains two AP endonucleases: MtbXthA and MtbNfo members of the exonuclease III and endonuclease IV families, which are exemplified by Escherichia coli Xth and Nfo, respectively. It has been shown that both MtbXthA and MtbNfo contain AP endonuclease and 3'→5' exonuclease activities. However, it remains unclear whether these enzymes hold 3'-repair phosphodiesterase and nucleotide incision repair (NIR) activities. Here, we report that both mycobacterial enzymes have 3'-repair phosphodiesterase and 3'-phosphatase, and MtbNfo contains in addition a very weak NIR activity. Interestingly, depending on pH, both enzymes require different concentrations of divalent cations: 0.5mM MnCl2 at pH 7.6 and 10 mM at pH 6.5. MtbXthA requires a low ionic strength and 37 °C, while MtbNfo requires high ionic strength (200 mM KCl) and has a temperature optimum at 60 °C. Point mutation analysis showed that D180 and N182 in MtbXthA and H206 and E129 in MtbNfo are critical for enzymes activities. The steady-state kinetic parameters indicate that MtbXthA removes 3'-blocking sugar-phosphate and 3'-phosphate moieties at DNA strand breaks with an extremely high efficiency (kcat/KM=440 and 1280 μM(-1)∙min(-1), respectively), while MtbNfo exhibits much lower 3'-repair activities (kcat/KM=0.26 and 0.65 μM(-1)∙min(-1), respectively). Surprisingly, both MtbXthA and MtbNfo exhibited very weak AP site cleavage activities, with kinetic parameters 100- and 300-fold lower, respectively, as compared with the results reported previously. Expression of MtbXthA and MtbNfo reduced the sensitivity of AP endonuclease-deficient E. coli xth nfo strain to methylmethanesulfonate and H2O2 to various degrees. Taken together, these data establish the DNA substrate specificity of M. tuberculosis AP endonucleases and suggest their possible role

Inhibition and recovery of the replication of depurinated parvovirus DNA in mouse fibroblasts

International Nuclear Information System (INIS)

Vos, J.M.; Avalosse, B.; Su, Z.Z.; Rommelaere, J.

1984-01-01

Apurinic sites were introduced in the single-stranded DNA of parvovirus minute-virus-of-mice (MVM) and their effect on viral DNA synthesis was measured in mouse fibroblasts. Approximately one apurinic site per viral genome, is sufficient to block its replication in untreated cells. The exposure of host cells to a sublethal dose of UV-light 15 hours prior to virus infection, enhances their ability to support the replication of depurinated MVM. Cell preirradiation induces the apparent overcome of 10-15% of viral DNA replication blocks. These results indicate that apurinic sites prevent mammalian cells from replicating single-stranded DNA unless a recovery process is activated by cell UV-irradiation

Selective inhibition by methoxyamine of the apurinic/apyrimidinic endonuclease activity associated with pyrimidine dimer-DNA glycosylases from Micrococcus luteus and bacteriophage T4

International Nuclear Information System (INIS)

Liuzzi, M.; Weinfeld, M.; Paterson, M.C.

1987-01-01

The UV endonucleases from Micrococcus luteus and bacteriophage T4 possess two catalytic activities specific for the site of cyclobutane pyrimidine dimers in UV-irradiated DNA: a DNA glycosylase that cleaves the 5'-glycosyl bond of the dimerized pyrimidines and an apurinic/apyrimidinic (AP) endonuclease that thereupon incises the phosphodiester bond 3' to the resulting apyrimidinic site. The authors have explored the potential use of methoxyamine, a chemical that reacts at neutral pH with AP sites in DNA, as a selective inhibitor of the AP endonuclease activities residing in the M. luteus and T4 enzymes. The presence of 50 mM methoxyamine during incubation of UV-treated, [ 3 H]thymine-labeled poly(dA) x poly(dT) with either enzyme preparation was found to protect completely the irradiated copolymer from endonucleolytic attack at dimer sites, as assayed by yield of acid-soluble radioactivity. In contrast, the dimer-DNA glycosylase activity of each enzyme remained fully functional, as monitored retrospectively by release of free thymine after either photochemical-(5 kJ/m 2 , 254 nm) or photoenzymic- (Escherichia coli photolyase plus visible light) induced reversal of pyrimidine dimers in the UV-damaged substrate. The data demonstrate that the inhibition of the strand-incision reaction arises because of chemical modification of the AP sites and is not due to inactivation of the enzyme by methoxyamine. The results, combined with earlier findings for 5'-acting AP endonucleases, strongly suggest that methoxyamine is a highly specific inhibitor of virtually all AP endonucleases, irrespective of their modes of action, and may therefore prove useful in a wide variety of DNA repair studies

The replicative DNA polymerase of herpes simplex virus 1 exhibits apurinic/apyrimidinic and 5′-deoxyribose phosphate lyase activities

Science.gov (United States)

Bogani, Federica; Boehmer, Paul E.

2008-01-01

Base excision repair (BER) is essential for maintaining genome stability both to counter the accumulation of unusual bases and to protect from base loss in the DNA. Herpes simplex virus 1 (HSV-1) is a large dsDNA virus that encodes its own DNA replication machinery, including enzymes involved in nucleotide metabolism. We report on a replicative family B and a herpesvirus-encoded DNA Pol that possesses DNA lyase activity. We have discovered that the catalytic subunit of the HSV-1 DNA polymerase (Pol) (UL30) exhibits apurinic/apyrimidinic (AP) and 5′-deoxyribose phosphate (dRP) lyase activities. These activities are integral to BER and lead to DNA cleavage on the 3′ side of abasic sites and 5′-dRP residues that remain after cleavage by 5′-AP endonuclease. The UL30-catalyzed reaction occurs independently of divalent cation and proceeds via a Schiff base intermediate, indicating that it occurs via a lyase mechanism. Partial proteolysis of the Schiff base shows that the DNA lyase activity resides in the Pol domain of UL30. These observations together with the presence of a virus-encoded uracil DNA glycosylase indicates that HSV-1 has the capacity to perform critical steps in BER. These findings have implications on the role of BER in viral genome maintenance during lytic replication and reactivation from latency. PMID:18695225

Activation of apurinic/apyrimidinic endonuclease in human cells by reactive oxygen species and its correlation with their adaptive response to genotoxicity of free radicals

OpenAIRE

Ramana, Chilakamarti V.; Boldogh, Istvan; Izumi, Tadahide; Mitra, Sankar

1998-01-01

Apurinic/apyrimidinic (AP) endonuclease (APE; EC 4.2.99.18) plays a central role in repair of DNA damage due to reactive oxygen species (ROS) because its DNA 3′-phosphoesterase activity removes 3′ blocking groups in DNA that are generated by DNA glycosylase/AP-lyases during removal of oxidized bases and by direct ROS reaction with DNA. The major human APE (APE-1) gene is activated selectively by sublethal levels of a variety of ROS and ROS generators, including ionizing radiation, but not by ...

Designing a responsive web site

OpenAIRE

Fejzić , Diana

2016-01-01

Due to the increasing prevalence of smartphones and tablet computers design became a crucial part of web design. For a user, responsive web design enables the best user experience, regardless of whether a user is visiting the site via a mobile phone, a tablet or a computer. This thesis covers the process of planning, designing and responsive web site development, for a fictitious company named “Creative Design d.o.o.”, with the help of web technologies. In the initial part of the thesis, w...

Site-specific design optimization of wind turbines

DEFF Research Database (Denmark)

Fuglsang, P.; Bak, C.; Schepers, J.G.

2002-01-01

This article reports results from a European project, where site characteristics were incorporated into the design process of wind turbines, to enable site-specific design. Two wind turbines of different concept were investigated at six different sites comprising normal flat terrain, offshore...... and complex terrain wind farms. Design tools based on numerical optimization and aeroelastic calculations were combined with a cost model to allow optimization for minimum cost of energy. Different scenarios were optimized ranging from modifications of selected individual components to the complete design...... of a new wind turbine. Both annual energy yield and design-determining loads depended on site characteristics, and this represented a potential for site-specific design. The maximum variation in annual energy yield was 37% and the maximum variation in blade root fatigue loads was 62%. Optimized site...

Characterization of a depurinated-DNA purine-base-insertion activity from Drosophila.

Science.gov (United States)

Deutsch, W A; Spiering, A L

1985-01-01

An activity that binds preferentially to depurinated DNA and inserts purines into those sites was partially purified from Drosophila melanogaster embryos. The protein has a sedimentation coefficient of 4.9 S and is devoid of AP (apurinic/apyrimidinic) endonuclease activity. Upon incorporation of purines into apurinic DNA, the number of alkali-labile sites decreases, thus establishing the conversion of depurinated sites into normal nucleotides. The activity requires K+, and is totally inhibited by caffeine or EDTA. Guanine is specifically incorporated into partially depurinated poly(dG-dC) and adenine is specifically incorporated into poly(dA-dT), thus demonstrating the apparent template specificity of the enzyme. PMID:2417589

Quantum mechanical design of enzyme active sites.

Science.gov (United States)

Zhang, Xiyun; DeChancie, Jason; Gunaydin, Hakan; Chowdry, Arnab B; Clemente, Fernando R; Smith, Adam J T; Handel, T M; Houk, K N

2008-02-01

The design of active sites has been carried out using quantum mechanical calculations to predict the rate-determining transition state of a desired reaction in presence of the optimal arrangement of catalytic functional groups (theozyme). Eleven versatile reaction targets were chosen, including hydrolysis, dehydration, isomerization, aldol, and Diels-Alder reactions. For each of the targets, the predicted mechanism and the rate-determining transition state (TS) of the uncatalyzed reaction in water is presented. For the rate-determining TS, a catalytic site was designed using naturalistic catalytic units followed by an estimation of the rate acceleration provided by a reoptimization of the catalytic site. Finally, the geometries of the sites were compared to the X-ray structures of related natural enzymes. Recent advances in computational algorithms and power, coupled with successes in computational protein design, have provided a powerful context for undertaking such an endeavor. We propose that theozymes are excellent candidates to serve as the active site models for design processes.

PHWR safety: design, siting and construction

International Nuclear Information System (INIS)

Sharma, V.K.

2002-01-01

In all activities associated with NPPs viz. siting, design, construction, commissioning and operation, safety is given overriding importance. The safety design principles of PHWRs are based on defence-in-depth approach, physical and functional separation between process and safety systems and also among various safety systems, redundancy to meet single failure criteria and postulation of a number of design basis events for which the plant must be designed. Apart from engineered safety systems, PHWRs have inherent characteristics which contribute to safety. In siting of a NPP, it is required to ensure that the given site does not pose undue radiological hazard to public and the environment both during normal operation as well as during and following an accident condition. For this purpose, all site related external events, both natural and man induced, are assessed for their effect on the plant and are considered as part of the design basis. Possible radiological impact of the NPP on environment and surrounding population is assessed and ensured to be within acceptable limits. During construction phase, it is essential that the NPP be built in accordance with design intent and with required quality of workmanship to ensure that the NPP will remain safe during all states of operation. This is achieved through careful execution and QA activities encompassing all aspects of component fabrication at manufacturer works, civil construction, site erection, assembly, and commissioning. Future trends in nuclear safety will continue to be based on existing principles which have proved to be sound. These will be further strengthened by features such as increasing use of passive means of performing safety functions and a more explicit treatment of severe accidents. (author)

A User-centered Model for Web Site Design

Science.gov (United States)

Kinzie, Mable B.; Cohn, Wendy F.; Julian, Marti F.; Knaus, William A.

2002-01-01

As the Internet continues to grow as a delivery medium for health information, the design of effective Web sites becomes increasingly important. In this paper, the authors provide an overview of one effective model for Web site design, a user-centered process that includes techniques for needs assessment, goal/task analysis, user interface design, and rapid prototyping. They detail how this approach was employed to design a family health history Web site, Health Heritage . This Web site helps patients record and maintain their family health histories in a secure, confidential manner. It also supports primary care physicians through analysis of health histories, identification of potential risks, and provision of health care recommendations. Visual examples of the design process are provided to show how the use of this model resulted in an easy-to-use Web site that is likely to meet user needs. The model is effective across diverse content arenas and is appropriate for applications in varied media. PMID:12087113

Formation and reparation of the AP-sites into DNA from the gamma-irradiated embryo of bombyx mori

International Nuclear Information System (INIS)

Agaev, F.A.; Gaziyev, A.I.

2002-01-01

Full text: It is well known that radiosensitivity of an organism is in dependence on the DNA reparation systems functioning into cells. Sharp difference in the radioresistance of silkworm embryo at different stage of growth showed by us earlier (Agaev F.A. et al, 1991) can provide to suggest that DNA reparation system into cells of 3-daily embryo (more radiosensitive stage) and 7-daily embryo (more radioresistance stage) may be functioning with various efficiency. It was shown that quantity of the AP-sites (i.e. apurine and apirimidine sites) registered into DNA of 3-daily embryo is 1,2 - 1,4 time more, that into DNA of 7-daily embryo g-irradiated at the same dozes. The increasing of the difference between the registered AP-sites into DNA of 3- and 7-daily embryo has been observed also at the increasing of the radiation doze. At the postradiation incubation of the 3- and 7- daily embryo the lowering of AP-sites quantity into DNA was observed. This fact allowed to testify that the reparation system of damages, such as DNA-apurinization and apirimidinization are functioned into these embryo cells. At the same time the rate of the AP-sites reparation into embryo cells is varied. For example, the remanent quantity of AP-sites into DNA of 7-daily embryo after 45 min of postradiation period consists of 30% those registered immediately after embryo irradiation. The remanent quantity of AP-sites into DNA of 3-daily embryo is lowered on 50%. The difference in the rate of cells reparation is keeping at the constant level irrespective of g-irradiation doze. The binding reaction between the /14 centigrade/-methoxyamine and AP-sites in DNA in vitro has been showed that the reparation time of the 50% AP-sites for 3-daily embryo is 45 min and for 7-daily embryo is 30 min in respective to registered value at once after 100 Gy irradiation doze. In spite of essential difference in the both AP-sites formation into DNA of 3- and 7-daily embryo at once after irradiation and the

Curcumin and EGCG Suppress Apurinic/Apyrimidinic Endonuclease 1 and Induce Complete Remission in B-cell Non-Hodgkin's lymphoma Patients

Directory of Open Access Journals (Sweden)

Hashem M. Neenaa

2011-12-01

Full Text Available ABSTRACT:Background: Follicular lymphoma (FL is the most common subtype of indolent lymphoma. FL is still considered to be an incurable disease and palliation of symptoms is an acceptable approach to the expected pattern of repeated relapses due to developing resistance to chemotherapy agents. Apurinic/apyrimidinic endonuclease/redox factor-1 (APE1/Ref-1 is a multifunctional protein involved in DNA base excision repair (BER of oxidative DNA damage and in redox regulation of a number of transcription factors. It was observed that cytoplasmic APE1 induced COX-2 expression through NF-êB activation. It has been shown that chemopreventive agents potentiate the efficacy of chemotherapy through the regulation of multiple signaling pathways, including NF-êB, c-Myc, cyclooxygenase-2, apoptosis, and others, suggesting a multitargeted nature of chemopreventive agents. We hypothesized that curcumin, a polyphenolic antioxidant derived from the spice turmeric, and epigallocatechin gallate (EGCG from green tea would potentiate the effect of chemotherapy in B-cell lymphoma.Objective: We examined the role of human apurinic/apyrimidinic endonuclease 1 (APE1 in resistance and prognosis in patients with FL. Our major objective was to update the safety and efficacy results of the antitumor effect of combination of curcumin and EGCG therapy in relapsed or resistant indolent or transformed non-Hodgkin follicular lymphoma patients and their peripheral blood mononuclear cells (PBMCs compared with healthy donors’ controls.Methods: Thirty patients with FL with over-expression of constitutive active NF-êB in their PBMCs received regular CHOP and consumed capsules compatible with curcumin doses between 0.9 and 5.4 g daily for up to 9 months and 9.0 g/day green tea whole extract "1000 mg tablets of green tea whole extract containing 200 mg EGCG. We designed a dose-escalation Functional Foods in Health and Disease 2011, 1(12:525-544 study to explore the efficacy of CHOP

Haplotype-based case-control study between human apurinic/apyrimidinic endonuclease 1/redox effector factor-1 gene and cerebral infarction.

Science.gov (United States)

Naganuma, Takahiro; Nakayama, Tomohiro; Sato, Naoyuki; Fu, Zhenyan; Yamaguchi, Mai; Soma, Masayoshi; Aoi, Noriko; Usami, Ron; Doba, Nobutaka; Hinohara, Shigeaki

2009-10-01

The aim of this study was to investigate the relationship between cerebral infarction (CI) and the human apurinic/apyrimidinic endonuclease 1/redox effector factor-1 (APE1/REF-1) gene using single-nucleotide polymorphisms (SNPs) and a haplotype-based case-control study. We selected 5 SNPs in the human APE1/REF1 gene (rs1760944, rs3136814, rs17111967, rs3136817 and rs1130409), and performed case-control studies in 177 CI patients and 309 control subjects. rs17111967 was found to have no heterogeneity in Japanese. The overall distribution of the haplotype-based case-control study constructed by rs1760944, rs3136814 and rs1130409 showed a significant difference. The frequency of the G-C-T haplotype was significantly higher in the CI group than in the control group (2.5% vs. 0.0%, p>0.001). Based on the results of the haplotype-based case-control-study, the G-C-T haplotype may be a genetic marker of CI, and the APE1/REF-1 gene may be a CI susceptibility gene.

SLAC site design aesthetics

International Nuclear Information System (INIS)

Hall, F.F.

1985-10-01

Stanford Linear Accelerator Center (SLAC) is a single mission laboratory dedicated to basic research in high energy particle physics. SLAC site also houses Stanford Synchrotron Radiation Laboratory (SSRL) which is a multi-mission laboratory for research using beams of ultraviolet light and low energy photons as emitted tangentially from SLAC colliding beam facilities. This paper discusses various aspects of SLAC site design aesthetics under the following headings: (1) imposed footprint of SLAC, (2) description of selected site, (3) use of earth cover for radiation and sight screens, (4) use of landscaping for cosmetic purposes, (5) use of exterior paint colors to soften SLAC impact on neighbors, (6) relocation of SLAC main entrance, (7) relocation of SLAC collider arcs and experimental hall, (8) parking lots and storage yards, and (9) land use zoning at SLAC

In vitro enzymatic studies on the nature and repair of x-ray-induced damages in DNA. Final report

International Nuclear Information System (INIS)

Wallace, S.S.

1981-03-01

An enzyme has been purified some 4000 fold from Escherichia coli which recognizes alkali stable base damages in x-irradiated DNA. The enzyme has broad specificity incising: DNA damaged by OsO 4 which produces thymine glycols, DNA treated with heat and acid which produces apurinic sites, and DNA uv-irradiated with high fluences which produces a variety of damages including the above. These activities co-chromatograph through Fraction VII the most purified form; however, the optimum reaction parameters differ among the various substrates suggesting the presence of more than one active site. Similar studies have been done with Saccharomyces cerevisiae. Several apurinic activities have been elucidated in this organism, one of which, Endonuclease E, has been purified over 1000 fold. Endonuclease E has been characterized with respect to various reaction parameters as well as by gel electrophoresis. Both the E. coli and yeast enzymes have been used to quantify DNA damage. Apurinic PM2 DNA and OsO 4 -treated PM2 DNA have also been used in a transfection system to estimate the inactivation efficiencies of AP sites and thymine glycols. AP sites have a relatively high inactivation efficiency and contribute about 15% to the inactivation of x-irradiated PM2 phage while thymine glycols contribute significantly less

WSDM : A user-centred design method for web sites

NARCIS (Netherlands)

de Troyer, O.M.F.; Leune, C.J.

1998-01-01

WSDM is a user-centered method for the design of kiosk Web Sites. By explicitly starting from the requirements of the users or visitors, WSDM solves Web site problems that are primarily caused by that fact that a site has no underlying design at all, or that the design is mostly data-driven.

Beyond Trust: Web Site Design Preferences Across Cultures

OpenAIRE

Dianne Cyr; Carole Bonanni; John Bowes; Joe Ilsever

2005-01-01

The growth of Internet shopping motivates a better understanding of how e-loyalty is built online between businesses and consumers. In this study, Web site design and culture are advanced as important to Web site trust, Web site satisfaction, and e-loyalty in online business relationships. Based on data collected in Canada, the U.S., Germany, and Japan, the research considers (1) examining within culture preferences for design elements of a local vs. a foreign Web site and subsequent particip...

Designation of facility usage categories for Hanford Site facilities

International Nuclear Information System (INIS)

Wodrich, D.; Ellingson, D.; Scott, M.; Schade, A.

1991-01-01

This report summarizes the Hanford Site methodology used to ensure facility compliance with the natural phenomena design criteria set forth in the US Department of Energy orders and guidance. In particular, the Hanford Site approach to designating a suitable facility open-quotes Usage Category,close quotes is presented. The current Hanford Site methodology for Usage Category designation is based on an engineered feature's safety function and on the feature's assigned Safety Class. At the Hanford Site, Safety Class assignments are deterministic in nature and are based on the consequences of failure, without regard to the likelihood of occurrence. The report also proposes a risk-based approach to Usage Category designation, which is being considered for future application at the Hanford Site. To establish a proper Usage Category designation, the safety analysis and engineering design processes must be coupled. This union produces a common understanding of the safety function(s) to be accomplished by the design feature(s) and a sound basis for the assignment of Usage Categories to the appropriate systems, structures, and components

The contribution of DNA apurinic/apyrimidinic endonuclease genotype and smoking habit to Taiwan lung cancer risk.

Science.gov (United States)

Chen, Wei-Chun; Tsai, Chia-Wen; Hsia, Te-Chun; Chang, Wen-Shin; Lin, Liang-Yi; Liang, Shinn-Jye; Tu, Chih-Yen; Cheng, Wei-Erh; Chen, Hung-Jen; Wang, Shu-Ming; Bau, da-Tian

2013-06-01

To evaluate the association and interaction of genotypic polymorphism the gene for DNA-apurinic/apyrimidinic endonuclease (APEX1) with personal smoking habit and lung cancer risk in Taiwan, the polymorphic variants of APEX1, Asp(148)Glu (rs1130409), were analyzed in association with lung cancer risk, and their joint effect with personal smoking habits on lung cancer susceptibility was discussed. In this hospital-based case-control study, 358 patients with lung cancer and 716 cancer-free controls, frequency-matched by age and sex, were recruited and genotyped by polymerase chain reaction and restriction fragment length polymorphism (PCR-RFLP). The results showed that the percentages of TT, TG and GG APEX1 Asp(148)Glu genotypes were not significantly different at 43.0%, 41.1% and 15.9% in the lung cancer patient group and 39.9%, 46.1% and 14.0% in non-cancer control group, respectively. We further analyzed the genetic-lifestyle effects on lung cancer risk and found the contribution of APEX1 Asp(148)Glu genotypes to lung cancer susceptibility was neither enhanced in the cigarette smokers nor in the non-smokers (p=0.3550 and 0.8019, respectively). Our results provide evidence that the non-synonymous polymorphism of APEX1 Asp(148)Glu may not be directly associated with lung cancer risk, nor enhance the effects of smoking habit on lung cancer development.

Designation of facility usage categories for Hanford Site facilities

International Nuclear Information System (INIS)

Woodrich, D.D.; Ellingson, D.R.; Scott, M.A.; Schade, A.R.

1991-10-01

This report summarizes the Hanford Site methodology used to ensure facility compliance with the natural phenomena design criteria set forth in the US Department of Energy Orders and guidance. The current Hanford Site methodology for Usage Category designation is based on an engineered feature's safety function and on the feature's assigned Safety Class. At the Hanford Site, Safety Class assignments are deterministic in nature and are based on teh consequences of failure, without regard to the likelihood of occurrence. The report also proposes a risk-based approach to Usage Category designation, which is being considered for future application at the Hanford Site. To establish a proper Usage Category designation, the safety analysis and engineering design processes must be coupled. This union produces a common understanding of the safety function(s) to be accomplished by the design feature(s) and a sound basis for the assignment of Usage Categories to the appropriate systems, structures, and components. 4 refs., 9 figs., 1 tab

Experimental site and design

Energy Technology Data Exchange (ETDEWEB)

Guenette, C. C. [SINTEF Applied Cemistry, Trondheim (Norway)

1999-08-01

Design and site selection criteria for the Svalbard oil spill experiments are described. All three experimental sites have coarse and mixed sediment beaches of sand and pebble; within each site wave exposure is very similar; along-shore and across-shore sediment characteristics are also relatively homogeneous. Tidal range is in the order of 0.6 m at neaps, and 1.8 m at springs. All three sites are open to wave action and are ice-free during the experimental period of mid-July to mid-October. Study plots at each site were selected for different treatments from within the continuous stretch of oiled shoreline, with oiled buffer zones between plots and at either end of the oiled zone. Treatments included mixing (tilling), sediment relocation (surf washing) and bioremediation (nutrient enrichment). Measurements and observations were carried out during the summers of 1997 and 1998. The characteristics measured were: wave and wind conditions; beach topography and elevation; sediment grain size distribution; mineral fines size distribution and mineral composition; background hydrocarbons; concentration of oil within experimental plots and the rate of oil loss over time; depth of oil penetration and thickness of the oiled sediment layer; oil concentration and toxicity of near-shore benthic sediments; mineral composition of suspended particulate material captured in sub-tidal sediment traps; and oil-fines interaction in near-shore water samples. 1 fig.

Experimental site and design

Energy Technology Data Exchange (ETDEWEB)

Guenette, C. C. [SINTEF Applied Cemistry, Trondheim (Norway)

1999-07-01

Design and site selection criteria for the Svalbard oil spill experiments are described. All three experimental sites have coarse and mixed sediment beaches of sand and pebble; within each site waveexposure is very similar; along-shore and across-shore sediment characteristics are also relatively homogeneous. Tidal range is in the order of 0.6 m at neaps, and 1.8 m at springs. All three sites are open to wave action and are ice-free during the experimental period of mid-July to mid-October. Study plots at each site were selected for different treatments from within the continuous stretch of oiled shoreline, with oiled buffer zones between plots and at either end of the oiled zone. Treatments included mixing (tilling), sediment relocation (surf washing) and bioremediation (nutrient enrichment). Measurements and observations were carried out during the summers of 1997 and 1998. The characteristics measured were: wave and wind conditions; beach topography and elevation; sediment grain size distribution; mineral fines size distribution and mineral composition; background hydrocarbons; concentration of oil within experimental plots and the rate of oil loss over time; depth of oil penetration and thickness of the oiled sediment layer; oil concentration and toxicity of near-shore benthic sediments; mineral composition of suspended particulate material captured in sub-tidal sediment traps; and oil-fines interaction in near-shore water samples. 1 fig.

Apurinic/apyrimidinic endonucleases of Mycobacterium tuberculosis protect against DNA damage but are dispensable for the growth of the pathogen in guinea pigs.

Science.gov (United States)

Puri, Rupangi Verma; Reddy, P Vineel; Tyagi, Anil K

2014-01-01

In host cells, Mycobacterium tuberculosis encounters an array of reactive molecules capable of damaging its genome. Non-bulky DNA lesions are the most common damages produced on the exposure of the pathogen to reactive species and base excision repair (BER) pathway is involved in the repair of such damage. During BER, apurinic/apyrimidinic (AP) endonuclease enzymes repair the abasic sites that are generated after spontaneous DNA base loss or by the action of DNA glycosylases, which if left unrepaired lead to inhibition of replication and transcription. However, the role of AP endonucleases in imparting protection against DNA damage and in the growth and pathogenesis of M.tuberculosis has not yet been elucidated. To demonstrate the biological significance of these enzymes in M.tuberculosis, it would be desirable to disrupt the relevant genes and evaluate the resulting mutants for their ability to grow in the host and cause disease. In this study, we have generated M.tuberculosis mutants of the base excision repair (BER) system, disrupted in either one (MtbΔend or MtbΔxthA) or both the AP endonucleases (MtbΔendΔxthA). We demonstrate that these genes are crucial for bacteria to withstand alkylation and oxidative stress in vitro. In addition, the mutant disrupted in both the AP endonucleases (MtbΔendΔxthA) exhibited a significant reduction in its ability to survive inside human macrophages. However, infection of guinea pigs with either MtbΔend or MtbΔxthA or MtbΔendΔxthA resulted in the similar bacillary load and pathological damage in the organs as observed in the case of infection with wild-type M.tuberculosis. The implications of these observations are discussed.

Apurinic/apyrimidinic endonucleases of Mycobacterium tuberculosis protect against DNA damage but are dispensable for the growth of the pathogen in guinea pigs.

Directory of Open Access Journals (Sweden)

Rupangi Verma Puri

Full Text Available In host cells, Mycobacterium tuberculosis encounters an array of reactive molecules capable of damaging its genome. Non-bulky DNA lesions are the most common damages produced on the exposure of the pathogen to reactive species and base excision repair (BER pathway is involved in the repair of such damage. During BER, apurinic/apyrimidinic (AP endonuclease enzymes repair the abasic sites that are generated after spontaneous DNA base loss or by the action of DNA glycosylases, which if left unrepaired lead to inhibition of replication and transcription. However, the role of AP endonucleases in imparting protection against DNA damage and in the growth and pathogenesis of M.tuberculosis has not yet been elucidated. To demonstrate the biological significance of these enzymes in M.tuberculosis, it would be desirable to disrupt the relevant genes and evaluate the resulting mutants for their ability to grow in the host and cause disease. In this study, we have generated M.tuberculosis mutants of the base excision repair (BER system, disrupted in either one (MtbΔend or MtbΔxthA or both the AP endonucleases (MtbΔendΔxthA. We demonstrate that these genes are crucial for bacteria to withstand alkylation and oxidative stress in vitro. In addition, the mutant disrupted in both the AP endonucleases (MtbΔendΔxthA exhibited a significant reduction in its ability to survive inside human macrophages. However, infection of guinea pigs with either MtbΔend or MtbΔxthA or MtbΔendΔxthA resulted in the similar bacillary load and pathological damage in the organs as observed in the case of infection with wild-type M.tuberculosis. The implications of these observations are discussed.

Adaptation of the ITER facility design to a Canadian site

International Nuclear Information System (INIS)

Smith, S.

2001-01-01

This paper presents the status of Canadian efforts to adapt the newly revised ITER facility design to suit the specific characteristics of the proposed Canadian site located in Clarington, west of Toronto, Ontario. ITER Canada formed a site-specific design team in 1999, comprising participants from three Canadian consulting companies to undertake this work. The technical aspects of this design activity includes: construction planning, geotechnical investigations, plant layout, heat sink design, electrical system interface, site-specific modifications and tie-ins, seismic design, and radwaste management. These areas are each addressed in this paper. (author)

A design method for an intuitive web site

Energy Technology Data Exchange (ETDEWEB)

Quinniey, M.L.; Diegert, K.V.; Baca, B.G.; Forsythe, J.C.; Grose, E.

1999-11-03

The paper describes a methodology for designing a web site for human factor engineers that is applicable for designing a web site for a group of people. Many web pages on the World Wide Web are not organized in a format that allows a user to efficiently find information. Often the information and hypertext links on web pages are not organized into intuitive groups. Intuition implies that a person is able to use their knowledge of a paradigm to solve a problem. Intuitive groups are categories that allow web page users to find information by using their intuition or mental models of categories. In order to improve the human factors engineers efficiency for finding information on the World Wide Web, research was performed to develop a web site that serves as a tool for finding information effectively. The paper describes a methodology for designing a web site for a group of people who perform similar task in an organization.

THE IMPORTANCE OF WEB DESIGN: VISUAL DESIGN EVALUATION OF DESTINATION WEB SITES

OpenAIRE

Fırlar, Belma; Okat Özdem, Özen

2013-01-01

As in the literature, the researchs about web site efficiency are mostly about site context. The analysis about function are mostly superficial. Whereas, controlling every little part of a web site respective is a necessity to show its efficiency. Here in this context in the study of perception and response event web sites that play an important role in visual design criteria are below the lens as featured and the web sites evaulated by heuristic evaluation method.The research focus of this s...

DENV gene of bacteriophage T4 codes for both pyrimidine dimer-DNA glycosylase and apyrimidinic endonuclease activities

International Nuclear Information System (INIS)

McMillan, S.; Edenberg, H.J.; Radany, E.H.; Friedberg, R.C.; Friedberg, E.C.

1981-01-01

Recent studies have shown that purified preparations of phage T4 UV DNA-incising activity (T4 UV endonuclease or endonuclease V of phase T4) contain a pyrimidine dimer-DNA glycosylase activity that catalyzes hydrolysis of the 5' glycosyl bond of dimerized pyrimidines in UV-irradiated DNA. Such enzyme preparations have also been shown to catalyze the hydrolysis of phosphodiester bonds in UV-irradiated DNA at a neutral pH, presumably reflecting the action of an apurinic/apyrimidinic endonuclease at the apyrimidinic sites created by the pyrimidine dimer-DNA glycosylase. In this study we found that preparations of T4 UV DNA-incising activity contained apurinic/apyrimidinic endonuclease activity that nicked depurinated form I simian virus 40 DNA. Apurinic/apyrimidinic endonuclease activity was also found in extracts of Escherichia coli infected with T4 denV + phage. Extracts of cells infected with T4 denV mutants contained significantly lower levels of apurinic/apyrimidinic endonuclease activity; these levels were no greater than the levels present in extracts of uninfected cells. Furthermore, the addition of DNA containing UV-irradiated DNA and T4 enzyme resulted in competition for pyrimidine dimer-DNA glycosylase activity against the UV-irradiated DNA. On the basis of these results, we concluded that apurinic/apyrimidinic endonuclease activity is encoded by the denV gene of phage T4, the same gene that codes for pyrimidine dimer-DNA glycosylase activity

Impact of Site Elevation on Mg Smelter Design

Science.gov (United States)

Baker, Phillip W.

Site elevation has many surprising and significant impacts on the engineering design of metallurgical plant of all types. Electrolytic magnesium smelters maybe built at high elevation for a variety of reasons including availability of raw material, energy or electric power. Because of the unit processes they typically involve, Mg smelters can be extensively impacted by site elevation. In this paper, generic examples of the design changes required to adapt a smelter originally designed for sea level to operate at 2700 m are presented. While the examples are drawn from a magnesium plant design case, these changes are generically applicable to all industrial plants utilizing similar unit processes irrespective of product.

Potentials for site-specific design of MW sized wind turbines

DEFF Research Database (Denmark)

Thomsen, K.; Fuglsang, P.; Schepers, G.

2001-01-01

The potential for site specific design of MW sized wind turbines is quantified by comparing design loads for wind turbines installed at a range of different sites. The sites comprise on-shore normal flat terrain stand-alone conditions and wind farm conditions together with offshore and mountainous...

Site characterization design and techniques used at the Southern Shipbuilding Corporation site

International Nuclear Information System (INIS)

Mueller, J.P.; Geraghty, C.A.; Moore, G.W.; Mullins, J.R.

1995-01-01

The Southern Shipbuilding Corporation (SSC) site is an inactive barge/ship manufacturing and repair facility situated on approximately 54 acres in Slidell, St. Tammany Parish, Louisiana. Two unlined surface impoundments (North and South impoundments) are situated on the northwest portion of the site and are surrounded on three sides by Bayou Bonfouca. These impoundments are the sources of carcinogenic polynuclear aromatic hydrocarbon (CPAH) contamination at the site. Inadequate containment has resulted in the release of impoundment wastes into the bayou. To evaluate potential response alternatives for the site, an Engineering Evaluation/Cost Analysis (EE/CA) field investigation was conducted from July through October 1994. A two phase sampling approach was used in combination with innovative and traditional sampling techniques, field screening technologies, and exploitation of the visual characteristics of the waste to determine the extent of waste migration with limited off-site laboratory confirmation. A skid-mounted mobile drilling unit, secured to a specialized sampling platform designed for multiple applications, was used for collection of sediment cores from the bayou as well as tarry sludge cores from the impoundments. Field screening of core samples was accomplished on site using an organic vapor analyzer and a total petroleum hydrocarbon (TPH) field analyzer. Pollutants of concern include metals, cyanide, dioxin, and organic compounds. This paper presents details on the sampling design and characterization techniques used to accomplish the EE/CA field investigation

Definitive design status of the SP-100 Ground Engineering System Test Site

International Nuclear Information System (INIS)

Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

1989-05-01

The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper

Definitive design status of the SP-100 Ground Engineering System Test Site

Energy Technology Data Exchange (ETDEWEB)

Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

1989-05-01

The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper.

NMR studies of abasic sites in DNA duplexes: deoxyadenosine stacks into the helix opposite the cyclic analog of 2-deoxyribose

International Nuclear Information System (INIS)

Kalnik, M.W.; Chang, C.N.; Grollman, A.P.; Patel, D.J.

1988-01-01

Proton and phosphorus NMR studies are reported for the complementary d(C-A-T-G-A-G-T-A-C) x d(G-T-A-C-F-C-A-T-G) nonanucleotide duplex (designated AP/sub F/ 9-mer duplex) which contains a stable abasic site analog, F, in the center of the helix. This oligodeoxynucleotide contains a modified tetrahydrofuran moiety, isosteric with 2-deoxyribofuranose, which serves as a structural analog of a natural apurinic/apyrimidinic site. Exchangeable and nonexchangeable base and sugar protons, including those located at the abasic site, have been assigned in the complementary AP/sub F/ 9-mer duplex by recording and analyzing two-dimensional phase-sensitive NOESY data sets in H 2 O and D 2 O solution at low temperature (0 0 C). These studies indicate that A5 inserts into the helix opposite the abasic site F14 and stacks with flanking G4 x C15 and G6 x C13 Watson-Crick base pairs. Base-sugar proton NOE connectivities were measured through G4-A5-G6 on the unmodified strand and between the base protons of C15 and the sugar protons of the 5'-flanking residue F14 on the modified strand. These studies establish that all glycosidic torsion angles are anti and that the helix is right-handed at and adjacent to the abasic site in the AP/sub F/ 9-mer duplex. Two of the 16 phosphodiester groups exhibit phosphorus resonances outside the normal spectral dispersion indicative of altered torsion angles at two of the phosphate groups in the backbone of the AP/sub F/ 9-mer duplex

Design surface covers: an approach to long-term waste site stabilization

International Nuclear Information System (INIS)

Beedlow, P.A.; Cadwell, L.L.; McShane, M.C.

1983-02-01

The wide range of existing environmental conditions, potential contaminants and available cover materials at waste disposal sites necessitates site-specific designing of surface covers for effective long-term erosion resistance. This paper presents a systematic approach to designing surface covers for hazardous waste repositories that can be tailored to conditions at any site. The approach consists of three phases: (1) an assessment, during which the degree of required surface protection (erosion potential) is determined; (2) a preliminary design that integrates surface cover design with the need to minimize transport of contaminants; and (3) a final design, where the cost and effectiveness of the surface cover are determined. 1 figure

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado

Energy Technology Data Exchange (ETDEWEB)

1992-02-01

This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

Apurinic/apyrimidinic endonuclease 1 regulates angiogenesis in a transforming growth factor β-dependent manner in human osteosarcoma.

Science.gov (United States)

Jiang, Xuan; Shan, Jinlu; Dai, Nan; Zhong, Zhaoyang; Qing, Yi; Yang, Yuxing; Zhang, Shiheng; Li, Chongyi; Sui, Jiangdong; Ren, Tao; Li, Mengxia; Wang, Dong

2015-10-01

Angiogenesis plays an important role in tumor growth and metastasis and has been reported to be inversely correlated with overall survival of osteosarcoma patients. It has been shown that apurinic/apyrimidinic endonuclease 1 (APE1), a dually functional protein possessing both base excision repair and redox activities, is involved in tumor angiogenesis, although these mechanisms are not fully understood. Our previous study showed that the expression of transforming growth factor β (TGFβ) was significantly reduced in APE1-deficient osteosarcoma cells. Transforming growth factor β promotes cancer metastasis through various mechanisms including immunosuppression, angiogenesis, and invasion. In the current study, we initially revealed that APE1, TGFβ, and microvessel density (MVD) have pairwise correlation in osteosarcoma tissue samples, whereas TGFβ, tumor size, and MVD were inversely related to the prognosis of the cohort. We found that knocking down APE1 in osteosarcoma cells resulted in TGFβ downregulation. In addition, APE1-siRNA led to suppression of angiogenesis in vitro based on HUVECs in Transwell and Matrigel tube formation assays. Reduced secretory protein level of TGFβ of culture medium also resulted in decreased phosphorylation of Smad3 of HUVECs. In a mouse xenograft model, siRNA-mediated silencing of APE1 downregulated TGFβ expression, tumor size, and MVD. Collectively, the current evidence indicates that APE1 regulates angiogenesis in osteosarcoma by controlling the TGFβ pathway, suggesting a novel target for anti-angiogenesis therapy in human osteosarcoma. © 2015 The Authors. Cancer Science published by Wiley Publishing Asia Pty Ltd on behalf of Japanese Cancer Association.

Prognostic value of human apurinic/apyrimidinic endonuclease 1 (APE1 expression in breast cancer.

Directory of Open Access Journals (Sweden)

Joohyun Woo

Full Text Available Human apurinic/apyrimidinic endonuclease 1 (APE1 is an essential protein for DNA base excision repair (BER and redox regulation. The ability of cancer cells to recognize DNA damage and initiate DNA repair is an important mechanism for therapeutic resistance. Several recent studies have suggested that APE1 expression levels and/or subcellular dysregulation may be used to indicate the sensitivity of tumors to radiotherapy or chemotherapy. In this study, we assessed the prognostic significance of APE1 and differences in APE1 expression levels according to breast cancer molecular subtypes. We analyzed formalin-fixed, paraffin-embedded tumor tissue sections from 243 cases diagnosed as invasive breast cancer at Ewha Womans University Medical Center between January 2003 and December 2008. Immunohistochemistry was performed and the nuclear level of APE1 was scored by taking into account the percentage of positive cells. Medical records were reviewed to investigate clinicopathologic characteristics. We found that nuclear APE1 high-level expression (proportion ≥50% in breast cancer showed a tendency towards unfavorable prognosis regarding disease-free survival (p = 0.093. However, there was no significant difference in overall survival between low and high-level expression groups (p = 0.294. Interestingly, within the Ki-67 low-level expression group, APE1 low-level expression was significantly associated with poor overall survival (p = 0.007. A significant positive correlation was observed between APE1 nuclear expression and estrogen receptor status (75.7% vs. 59.7%, p = 0.022. Also, the luminal A subtype was the most commonly observed breast cancer subtype in the APE1 high-level expression group (61.6% vs. 45.2%, p = 0.000. This study suggests that APE1 expression may be associated with breast cancer prognosis. In particular, its role as a prognostic factor would be significant for breast cancers with a low Ki-67 proliferation index

A reagentless electrochemiluminescent immunosensor for apurinic/apyrimidinic endonuclease 1 detection based on the new Ru(bpy){sub 3}{sup 2+}/bi-arginine system

Energy Technology Data Exchange (ETDEWEB)

Zhao, Min; Chai, Xi Deng Ya-Qin; Han, Jing; Gui, Guo-Feng; Yuan, Ruo, E-mail: yuanruo@swu.edu.cn; Zhuo, Ying, E-mail: yingzhuo@swu.edu.cn

2014-10-10

Highlights: • A reagentless ECL biosensor based on the new Ru(bpy){sub 3}{sup 2+}/bi-arginine system. • The successful preparation of bi-Arg/Au@Fe3O4–rGO as enhancer. • Using the APE-1 as target by the sandwich-type immunoassay format. - Abstract: Apurinic/apyrimidinic endonuclease 1 (APE-1), a kind of multifunctional protein widely-distributed in the body, plays an essential role in the DNA base excision repair and serves as multiple possible roles in the response of human cancer to radiotherapy and chemotherapy. In this work, an ultrasensitive solid-state electrochemiluminescence (ECL) immunosensor is designed to determine APE-1 based on the new Ru(bpy){sub 3}{sup 2+}/bi-arginine system. The bi-arginine (bi-Arg) is decorated on the Au nanoparticles functionalized magnetic Fe{sub 3}O{sub 4}/reduced graphene oxide (bi-Arg/Au@Fe{sub 3}O{sub 4}–rGO) according to the self-assembling and covalent cross-linking interaction to obtain the functionalized nanocomposite of bi-Arg/Au@Fe{sub 3}O{sub 4}–rGO. Herein, the bi-Arg/Au@Fe{sub 3}O{sub 4}–rGO plays not only an amplification label to enhance the ECL signal of Ru(bpy){sub 3}{sup 2+} due to the coreactant of bi-Arg but also an ideal nanocarrier to load numerous secondary antibody. Based on sandwich-type immunoassay format, this proposed method offers a linear range of 1.0 fg mL{sup −1}–5.0 pg mL{sup −1} and an estimated detection limit of 0.3 fg mL{sup −1} for the APE-1. Moreover, the reagentless ECL immunosensor also exhibits high sensitivity, excellent selectivity and good stability, which has greatly potential development and application in clinical diagnostics, immunology and biomedical research.

Direct detection and quantification of abasic sites for in vivo studies of DNA damage and repair

International Nuclear Information System (INIS)

Wang Yanming; Liu Lili; Wu Chunying; Bulgar, Alina; Somoza, Eduardo; Zhu Wenxia; Gerson, Stanton L.

2009-01-01

Use of chemotherapeutic agents to induce cytotoxic DNA damage and programmed cell death is a key strategy in cancer treatments. However, the efficacy of DNA-targeted agents such as temozolomide is often compromised by intrinsic cellular responses such as DNA base excision repair (BER). Previous studies have shown that BER pathway resulted in formation of abasic or apurinic/apyrimidinic (AP) sites, and blockage of AP sites led to a significant enhancement of drug sensitivity due to reduction of DNA base excision repair. Since a number of chemotherapeutic agents also induce formation of AP sites, monitoring of these sites as a clinical correlate of drug effect will provide a useful tool in the development of DNA-targeted chemotherapies aimed at blocking abasic sites from repair. Here we report an imaging technique based on positron emission tomography (PET) that allows for direct quantification of AP sites in vivo. For this purpose, positron-emitting carbon-11 has been incorporated into methoxyamine ([ 11 C]MX) that binds covalently to AP sites with high specificity. The binding specificity of [ 11 C]MX for AP sites was demonstrated by in vivo blocking experiments. Using [ 11 C]MX as a radiotracer, animal PET studies have been conducted in melanoma and glioma xenografts for quantification of AP sites. Following induction of AP sites by temozolomide, both tumor models showed significant increase of [ 11 C]MX uptake in tumor regions in terms of radioactivity concentration as a function of time, which correlates well with conventional aldehyde reactive probe (ARP)-based bioassays for AP sites.

Direct-to-consumer advertising via the Internet: the role of Web site design.

Science.gov (United States)

Sewak, Saurabh S; Wilkin, Noel E; Bentley, John P; Smith, Mickey C

2005-06-01

Recent attempts to propose criteria for judging the quality of pharmaceutical and healthcare Web sites do not distinguish between attributes of Web site design related to content and other attributes not related to the content. The Elaboration Likelihood Model from persuasion literature is used as a framework for investigating the effects of Web site design on consequents like attitude and knowledge acquisition. A between-subjects, 2 (high or low involvement)x2 (Web site designed with high or low aspects of visual appeal) factorial design was used in this research. College students were randomly assigned to these treatment groups yielding a balanced design with 29 observations per treatment cell. Analysis of variance results for the effects of involvement and Web site design on attitude and knowledge indicated that the interaction between the independent variables was not significant in both analyses. Examination of main effects revealed that participants who viewed the Web site with higher visual appeal actually had slightly lower knowledge scores (6.32) than those who viewed the Web site with lower visual appeal (7.03, F(1,112)=3.827, P=.053). Results of this research seem to indicate that aspects of Web site design (namely aspects of visual appeal and quality) may not play a role in attaining desired promotional objectives, which can include development of favorable attitudes toward the product and facilitating knowledge acquisition.

Status of small reactor designs without on-site refuelling

International Nuclear Information System (INIS)

2007-01-01

There is an ongoing interest in member states in the development and application of small and medium sized reactors (SMRs). In the near term, most new NPPs are likely to be evolutionary designs building on proven systems while incorporating technological advances and often the economics of scale, resulting from the reactor outputs of up to 1600 MW(e). For the longer term, the focus is on innovative designs aiming to provide increased benefits in the areas of safety and security, non-proliferation, waste management, resource utilization and economy, as well as to offer a variety of energy products and flexibility in design, siting and fuel cycle options. Many innovative designs are reactors within the small-to-medium size range, having an equivalent electric power less than 700 MW(e) or even less than 300 MW(e). A distinct trend in design and technology development, accounting for about half of the SMR concepts developed worldwide, is represented by small reactors without on-site refuelling. Such reactors, also known as battery-type reactors, could operate without reloading and shuffling of fuel in the core over long periods, from 5 to 25 years and beyond. Upon the advice and with the support of IAEA member states, within its Programme 1 'Nuclear Power, Fuel Cycle, and Nuclear Science', the IAEA provides a forum for the exchange of information by experts and policy makers from industrialized and developing countries on the technical, economic, environmental, and social aspects of SMRs development and implementation in the 21st century, and makes this information available to all interested Member States by producing status reports and other publications dedicated to advances in SMR technology. The objective of this report is to provide Member States, including those just considering the initiation of nuclear power programmes and those already having practical experience in nuclear power, with a balanced and objective information on important development trends and

Synthesis and binding properties of new selective ligands for the nucleobase opposite the AP site.

Science.gov (United States)

Abe, Yukiko; Nakagawa, Osamu; Yamaguchi, Rie; Sasaki, Shigeki

2012-06-01

DNA is continuously damaged by endogenous and exogenous factors such as oxidative stress or DNA alkylating agents. These damaged nucleobases are removed by DNA N-glycosylase and form apurinic/apyrimidinic sites (AP sites) as intermediates in the base excision repair (BER) pathway. AP sites are also representative DNA damages formed by spontaneous hydrolysis. The AP sites block DNA polymerase and a mismatch nucleobase is inserted opposite the AP sites by polymerization to cause acute toxicities and mutations. Thus, AP site specific compounds have attracted much attention for therapeutic and diagnostic purposes. In this study, we have developed nucleobase-polyamine conjugates as the AP site binding ligand by expecting that the nucleobase part would play a role in the specific recognition of the nucleobase opposite the AP site by the Watson-Crick base pair formation and that the polyamine part should contribute to the access of the ligand to the AP site by a non-specific interaction to the DNA phosphate backbone. The nucleobase conjugated with 3,3'-diaminodipropylamine (A-ligand, G-ligand, C-ligand, T-ligand and U-ligand) showed a specific stabilization of the duplex containing the AP site depending on the complementary combination with the nucleobase opposite the AP site; that is A-ligand to T, G-ligand to C, C-ligand to G, T- and U-ligand to A. The thermodynamic binding parameters clearly indicated that the specific stabilization is due to specific binding of the ligands to the complementary AP site. These results have suggested that the complementary base pairs of the Watson-Crick type are formed at the AP site. Copyright © 2012 Elsevier Ltd. All rights reserved.

Design characteristics of EU-APR1400 on-site power system

International Nuclear Information System (INIS)

Kim, D.H.; Kim, Y.S.; Kim, Y.S.

2014-01-01

In the global nuclear market, US and European design requirements have been largely used to develop the design of nuclear power plants(NPPs). The APR1400 design was developed on the basis of US regulatory guide and EPRI utility requirements document(URD). In order to enlarge the export market of APR1400, KHNP (Korea Hydro & Nuclear Power Co., Ltd) has developed the EU-APR1400 design which complies with the European nuclear design requirements. In this paper, the design characteristics of EU-APR1400 on-site power system developed according to the European design requirements of electrical power system are described. The European main design requirements of electrical power system involve 50 Hz rated frequency, 400/110 kV grid voltage, the application of the diversity and the redundancy, and so on. The EU-APR1400 on-site power system has been developed on the basis of these requirements. The representative designs include the redundancy, diversity, independence design, the emergency power supply design, the design for providing electrical power to the dedicated severe accident systems, and the design for European grid requirements. (author)

Brownfields Recommendations for Sustainable Site Design — Green Landscape Plan

Science.gov (United States)

The assessment of conditions contained in this report focuses on site-specific environmental and soil conditions that might affect recommendations related to sustainable landscaping and site design, stormwater management, and stormwater reuse.

Building arrangement and site layout design guides for on site low level radioactive waste storage facilities

International Nuclear Information System (INIS)

McMullen, J.W.; Feehan, M.J.

1986-01-01

Many papers have been written by AE's and utilities describing their onsite storage facilities, why they are needed, NRC regulations, and disposal site requirements. This paper discusses a typical storage facility and address the design considerations and operational aspects that are generally overlooked when designing and siting a low level radioactive waste storage facility. Some topics to be addressed are: 1. Container flexibility; 2. Modular expansion capabilities; 3. DOT regulations; 4. Meterological requirements; 5. OSHA; 6. Fire protection; 7. Floods; 8. ALARA

Preliminary site design for the SP-100 ground engineering test

International Nuclear Information System (INIS)

Cox, C.M.; Miller, W.C.; Mahaffey, M.K.

1986-04-01

In November, 1985, Hanford was selected by the Department of Energy (DOE) as the preferred site for a full-scale test of the integrated nuclear subsystem for SP-100. The Hanford Engineering Development Laboratory, operated by Westinghouse Hanford Company, was assigned as the lead contractor for the Test Site. The nuclear subsystem, which includes the reactor and its primary heat transport system, will be provided by the System Developer, another contractor to be selected by DOE in late FY-1986. In addition to reactor operations, test site responsibilities include preparation of the facility plus design, procurement and installation of a vacuum chamber to house the reactor, a secondary heat transport system to dispose of the reactor heat, a facility control system, and postirradiation examination. At the conclusion of the test program, waste disposal and facility decommissioning are required. The test site must also prepare appropriate environmental and safety evaluations. This paper summarizes the preliminary design requirements, the status of design, and plans to achieve full power operation of the test reactor in September, 1990

Computational design of trimeric influenza-neutralizing proteins targeting the hemagglutinin receptor binding site

Energy Technology Data Exchange (ETDEWEB)

Strauch, Eva-Maria; Bernard, Steffen M.; La, David; Bohn, Alan J.; Lee, Peter S.; Anderson, Caitlin E.; Nieusma, Travis; Holstein, Carly A.; Garcia, Natalie K.; Hooper, Kathryn A.; Ravichandran, Rashmi; Nelson, Jorgen W.; Sheffler, William; Bloom, Jesse D.; Lee, Kelly K.; Ward, Andrew B.; Yager, Paul; Fuller, Deborah H.; Wilson, Ian A.; Baker , David (UWASH); (Scripps); (FHCRC)

2017-06-12

Many viral surface glycoproteins and cell surface receptors are homo-oligomers1, 2, 3, 4, and thus can potentially be targeted by geometrically matched homo-oligomers that engage all subunits simultaneously to attain high avidity and/or lock subunits together. The adaptive immune system cannot generally employ this strategy since the individual antibody binding sites are not arranged with appropriate geometry to simultaneously engage multiple sites in a single target homo-oligomer. We describe a general strategy for the computational design of homo-oligomeric protein assemblies with binding functionality precisely matched to homo-oligomeric target sites5, 6, 7, 8. In the first step, a small protein is designed that binds a single site on the target. In the second step, the designed protein is assembled into a homo-oligomer such that the designed binding sites are aligned with the target sites. We use this approach to design high-avidity trimeric proteins that bind influenza A hemagglutinin (HA) at its conserved receptor binding site. The designed trimers can both capture and detect HA in a paper-based diagnostic format, neutralizes influenza in cell culture, and completely protects mice when given as a single dose 24 h before or after challenge with influenza.

Progress on building design and site layout, and preparation for procurement

International Nuclear Information System (INIS)

Haange, R.

2004-01-01

The ITER site layout and buildings retain many of the major features worked out for the original 1998 design of ITER. By mid-2001, the design had been adjusted to take account of the reductions in size of the tokamak and in the performance and capability of its supporting plant systems, with a view to providing a building construction cost reduction near the target of 50%. The present status of the site layout and buildings is that, with the exception of the hot cell building, designs are available for the ITER buildings and site layout, in different degrees of detail, ready for final review as soon as the drawings and 3D models have been updated. The ITER site layout is determined by the functions of the various plant systems provided in support of the ITER tokamak. These systems are located in different buildings on the ITER site. Changes in the plant layout inside buildings can, therefore, have an important impact on the overall site layout. The general layout of the site assumes electrical power comes in from the west, heat rejection is on the east, access into the main building for assembly is from the south, and removal of waste is from the north. These orientations are purely notional, determining only the relative positions. Both the European and Japanese potential ITER sites will most likely use seismic isolation of the main tokamak complex. As a result, the detailed design of these buildings and in particular the piping connections to them developed for the 'generic' ITER site will require redesign. Also, the footprint of the main tokamak complex will increase, and hence the layout of the utility tunnel network will have to be updated. A draft Site Facilities Procurement Specification has been written by the International Team. This will require considerable specific input when the site has been selected. Furthermore, the present site layout will have to be reviewed in detail. The generic site has been kept compact. Once a site is available, it may be

Activation of apurinic/apyrimidinic endonuclease in human cells by reactive oxygen species and its correlation with their adaptive response to genotoxicity of free radicals

Science.gov (United States)

Ramana, Chilakamarti V.; Boldogh, Istvan; Izumi, Tadahide; Mitra, Sankar

1998-01-01

Apurinic/apyrimidinic (AP) endonuclease (APE; EC 4.2.99.18) plays a central role in repair of DNA damage due to reactive oxygen species (ROS) because its DNA 3′-phosphoesterase activity removes 3′ blocking groups in DNA that are generated by DNA glycosylase/AP-lyases during removal of oxidized bases and by direct ROS reaction with DNA. The major human APE (APE-1) gene is activated selectively by sublethal levels of a variety of ROS and ROS generators, including ionizing radiation, but not by other genotoxicants—e.g., UV light and alkylating agents. Increased expression of APE mRNA and protein was observed both in the HeLa S3 tumor line and in WI 38 primary fibroblasts, and it was accompanied by translocation of the endonuclease to the nucleus. ROS-treated cells showed a significant increase in resistance to the cytotoxicity of such ROS generators as H2O2 and bleomycin, but not to UV light. This “adaptive response” appears to result from enhanced repair of cytotoxic DNA lesions due to an increased activity of APE-1, which may be limiting in the base excision repair process for ROS-induced toxic lesions. PMID:9560228

Repository surface design site layout analysis

International Nuclear Information System (INIS)

Montalvo, H.R.

1998-01-01

The purpose of this analysis is to establish the arrangement of the Yucca Mountain Repository surface facilities and features near the North Portal. The analysis updates and expands the North Portal area site layout concept presented in the ACD, including changes to reflect the resizing of the Waste Handling Building (WHB), Waste Treatment Building (WTB), Carrier Preparation Building (CPB), and site parking areas; the addition of the Carrier Washdown Buildings (CWBs); the elimination of the Cask Maintenance Facility (CMF); and the development of a concept for site grading and flood control. The analysis also establishes the layout of the surface features (e.g., roads and utilities) that connect all the repository surface areas (North Portal Operations Area, South Portal Development Operations Area, Emplacement Shaft Surface Operations Area, and Development Shaft Surface Operations Area) and locates an area for a potential lag storage facility. Details of South Portal and shaft layouts will be covered in separate design analyses. The objective of this analysis is to provide a suitable level of design for the Viability Assessment (VA). The analysis was revised to incorporate additional material developed since the issuance of Revision 01. This material includes safeguards and security input, utility system input (size and location of fire water tanks and pump houses, potable water and sanitary sewage rates, size of wastewater evaporation pond, size and location of the utility building, size of the bulk fuel storage tank, and size and location of other exterior process equipment), main electrical substation information, redundancy of water supply and storage for the fire support system, and additional information on the storm water retention pond

On site PWR fuel inspection measurements for operational and design verification

International Nuclear Information System (INIS)

1996-01-01

The on-site inspection of irradiated Pressurized Water Reactor (PWR) fuel and Non-Fuel Bearing Components (NFBC) is typically limited to visual inspections during refuelings using underwater TV cameras and is intended primarily to confirm whether the components will continue in operation. These inspections do not normally provide data for design verification nor information to benefit future fuel designs. Japanese PWR utilities and Nuclear Fuel Industries Ltd. designed, built, and performed demonstration tests of on-site inspection equipment that confirms operational readiness of PWR fuel and NFBC and also gathers data for design verification of these components. 4 figs, 3 tabs

Brownfields Green Avenue Sites: Technical Memorandum - Conceptual Design for Sustainable Redevelopment

Science.gov (United States)

This technical memorandum briefly describes the site and proposed conceptual site plan, indicates conceptual design considerations, specifies recommended green and sustainable features, and offers other recommendations

10 CFR 435.6 - Sustainable principles for siting, design and construction. [Reserved

Science.gov (United States)

2010-01-01

... 10 Energy 3 2010-01-01 2010-01-01 false Sustainable principles for siting, design and construction. [Reserved] 435.6 Section 435.6 Energy DEPARTMENT OF ENERGY ENERGY CONSERVATION ENERGY EFFICIENCY STANDARDS...-Rise Residential Buildings. § 435.6 Sustainable principles for siting, design and construction...

10 CFR 433.6 - Sustainable principles for siting, design and construction. [Reserved

Science.gov (United States)

2010-01-01

... 10 Energy 3 2010-01-01 2010-01-01 false Sustainable principles for siting, design and construction. [Reserved] 433.6 Section 433.6 Energy DEPARTMENT OF ENERGY ENERGY CONSERVATION ENERGY EFFICIENCY STANDARDS... BUILDINGS § 433.6 Sustainable principles for siting, design and construction. [Reserved] ...

OSU TOMF Program Site Selection and Preliminary Concept Design Report

Energy Technology Data Exchange (ETDEWEB)

Spadling, Steve [Oklahoma State Univ., Stillwater, OK (United States)

2012-05-10

The purpose of this report is to confirm the programmatic requirements for the new facilities, identify the most appropriate project site, and develop preliminary site and building concepts that successfully address the overall project goals and site issues. These new facilities will be designed to accommodate the staff, drivers and maintenance requirements for the future mixed fleet of passenger vehicles, Transit Style Buses and School Buses.

Design/licensing of on-site package for core component

International Nuclear Information System (INIS)

Ogasawara, K.; Chohzuka, T.; Shimura, T.; Kikuchi, T.; Fujiwara, R.; Karigome, S.; Takani, M.

1993-01-01

For storage of used core components which are produced from reactors, Tohoku EPCO decided to construct a site bunker at Onagawa site. It was also decided to develop and fabricate one packaging to transport core components from the reactor buildings to the site bunker. The packaging will be used within the power station; therefore, it shall comply with 'The Law for the Business of Electric Power' and relevant Notification. The main requirements of the packaging are as follows: 1) The number of contents, such as channel boxes and control rods, shall be as large as possible. 2) The weight and the outer dimensions of the packaging shall be within the limitation of the reactor building and the site bunker. 3) Materials shall be selected from those which have been already applied for existing packagings and utilized without any problems. 4) It shall be considered during design of trunnions that handling equipment, such as lifting beam, can be used for not only this packaging but also for existing spent fuel packagings. The design of the packaging is completed and has been licensed. The packaging is scheduled to be utilized from November, 1993. (J.P.N.)

Beyond Information Architecture: A Systems Integration Approach to Web-site Design

Directory of Open Access Journals (Sweden)

Krisellen Maloney

2017-09-01

Full Text Available Users' needs and expectations regarding access to information have fundamentally changed, creating a disconnect between how users expect to use a library Web site and how the site was designed. At the same time, library technical infrastructures include legacy systems that were not designedf or the Web environment. The authors propose a framework that combines elements of information architecture with approaches to incremental system design and implementation. The framework allows for the development of a Web site that is responsive to changing user needs, while recognizing the need for libraries to adopt a cost-effective approach to implementation and maintenance.

The content and design of Web sites : an empirical study

NARCIS (Netherlands)

Huizingh, EKRE

2000-01-01

To support the emergence of a solid knowledge base for analyzing Web activity, we have developed a framework to analyze and categorize the capabilities of Web sites. This distinguishes content from design. Content refers to the information, features, or services that are offered in the Web site,

Probabilistic site dependent design spectra for a NPP

International Nuclear Information System (INIS)

Chavez, M.; Arroyo, M.; Romo, M.P.

1985-01-01

A methodology is proposed to compute the design spectra for a NPP site. Near field earthquakes are included by using an appropriately scaled sample of response spectra. Site effects are considered through a probabilistic site response analysis in the frequency domain which considers nonlinear behaviour of soils. The uncertainties of the soil shear modulus, G, are introduced by using Rosenblueth's point estimates. Strong motion duration is treated by using sensitivity analysis. The procedure is applied to a NPP site and the results are: a) the USNCR R.G.1.60 underestimate the spectral amplitudes for frequencies of interest; b) the omission of the uncertainties on the G leads to under or over-estimate the spectral amplitudes at certain frequency bands; c) the effect of considering the actual strong motion duration instead of an average value is to reduce the peak spectral amplitudes by a ten per cent. (orig.)

Design considerations for on-site spent-fuel transfer systems

International Nuclear Information System (INIS)

Jones, R.H.; Jones, C.R.

1989-06-01

Studies on spent fuel shipping logistics and operation make it clear that the use of large casks, i.e., 100--125 tons, is superior to smaller casks of similar construction. This superiority manifests itself in both transportation and/or shipping economics and safety as well as reduced personnel exposure in the processing of the casks. An on-site system for the transfer of spent fuel from the storage pool to a large shipping or storage cask, as well as the transfer of spent fuel directly from a storage cask to a shipping cask, could bring the large cask benefits to those restricted reactors. Sensing the need to look more closely at this opportunity, EPRI contracted with S. Levy, Incorporated of Campbell, CA to develop a set of design considerations for such transfer systems. Rather then embark on another design study, EPRI decided to first identify the system considerations that must be factored into any design. The format for this effort presents both the Consideration and the Rationale for the consideration. The resulting work identified thirty-six General Considerations and two Special Considerations. The Considerations are in the form of mandatory requirements and desirable but nonmandatory requirements. Additionally, a brief economic study was performed to get a feel for the cost considerations of on-site transfers. The study results suggest a relatively narrow set of scenarios where on-site transfers are economically superior to alternatives. These scenarios generally involve the use of concrete casks as on-site storage devices

Biological consequences of potential repair intermediates of clustered base damage site in Escherichia coli

Energy Technology Data Exchange (ETDEWEB)

Shikazono, Naoya, E-mail: shikazono.naoya@jaea.go.jp [Japan Atomic Energy Agency, Advanced Research Science Center, 2-4 Shirakata-Shirane, Tokai-mura, Naka-gun, Ibaraki 319-1195 (Japan); O' Neill, Peter [Gray Institute for Radiation Oncology and Biology, University of Oxford, Roosevelt Drive, Oxford OX3 7DQ (United Kingdom)

2009-10-02

Clustered DNA damage induced by a single radiation track is a unique feature of ionizing radiation. Using a plasmid-based assay in Escherichia coli, we previously found significantly higher mutation frequencies for bistranded clusters containing 7,8-dihydro-8-oxoguanine (8-oxoG) and 5,6-dihydrothymine (DHT) than for either a single 8-oxoG or a single DHT in wild type and in glycosylase-deficient strains of E. coli. This indicates that the removal of an 8-oxoG from a clustered damage site is most likely retarded compared to the removal of a single 8-oxoG. To gain further insights into the processing of bistranded base lesions, several potential repair intermediates following 8-oxoG removal were assessed. Clusters, such as DHT + apurinic/apyrimidinic (AP) and DHT + GAP have relatively low mutation frequencies, whereas clusters, such as AP + AP or GAP + AP, significantly reduce the number of transformed colonies, most probably through formation of a lethal double strand break (DSB). Bistranded AP sites placed 3' to each other with various interlesion distances also blocked replication. These results suggest that bistranded base lesions, i.e., single base lesions on each strand, but not clusters containing only AP sites and strand breaks, are repaired in a coordinated manner so that the formation of DSBs is avoided. We propose that, when either base lesion is initially excised from a bistranded base damage site, the remaining base lesion will only rarely be converted into an AP site or a single strand break in vivo.

Biological consequences of potential repair intermediates of clustered base damage site in Escherichia coli

International Nuclear Information System (INIS)

Shikazono, Naoya; O'Neill, Peter

2009-01-01

Clustered DNA damage induced by a single radiation track is a unique feature of ionizing radiation. Using a plasmid-based assay in Escherichia coli, we previously found significantly higher mutation frequencies for bistranded clusters containing 7,8-dihydro-8-oxoguanine (8-oxoG) and 5,6-dihydrothymine (DHT) than for either a single 8-oxoG or a single DHT in wild type and in glycosylase-deficient strains of E. coli. This indicates that the removal of an 8-oxoG from a clustered damage site is most likely retarded compared to the removal of a single 8-oxoG. To gain further insights into the processing of bistranded base lesions, several potential repair intermediates following 8-oxoG removal were assessed. Clusters, such as DHT + apurinic/apyrimidinic (AP) and DHT + GAP have relatively low mutation frequencies, whereas clusters, such as AP + AP or GAP + AP, significantly reduce the number of transformed colonies, most probably through formation of a lethal double strand break (DSB). Bistranded AP sites placed 3' to each other with various interlesion distances also blocked replication. These results suggest that bistranded base lesions, i.e., single base lesions on each strand, but not clusters containing only AP sites and strand breaks, are repaired in a coordinated manner so that the formation of DSBs is avoided. We propose that, when either base lesion is initially excised from a bistranded base damage site, the remaining base lesion will only rarely be converted into an AP site or a single strand break in vivo.

Molecular Recognition of DNA Damage Sites by Apurinic/Apyrimidinic Endonucleases

Energy Technology Data Exchange (ETDEWEB)

Braun, W. A.

2005-07-28

The DNA repair/redox factor AP endonuclease 1 (APE1) is a multifunctional protein which is known to to be essential for DNA repair activity in human cells. Structural/functional analyses of the APE activity is thus been an important research field to assess cellular defense mechanisms against ionizing radiation.

New "persona" concept helps site designers cater to target user segments' needs.

Science.gov (United States)

2004-09-01

Using the relatively new "persona" design concept, Web strategists create a set of archetypical user characters, each one representing one of their site's primary audiences. Then, as their site is constructed or upgraded, they champion the personas, arguing on their behalf and forcing the design team to take each audience's needs and wants into account.

Conceptual design of a cover system for the degmay uranium tailings site

Energy Technology Data Exchange (ETDEWEB)

Vatsidin, Saidov; David, S. Kessel; Kim, Chang Lak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2016-06-15

The Republic of Tajikistan has ten former uranium mining sites. The total volume of all tailings is approximately 55 million tonnes, and the covered area is more than 200 hectares. The safe management of legacy uranium mining and tailing sites has become an issue of concern. Depending on the performance requirements and site-specific conditions (location in an arid, semiarid or humid region), a cover system for uranium tailings sites could be constructed using several material layers using both natural and man-made materials. The purpose of this study is to find a feasible cost-effective cover system design for the Degmay uranium tailings site which could provide a long period (100 years) of protection. The HELP computer code was used in the evaluation of potential Degmay cover system designs. As a result of this study, a cover system with 70 cm thick percolation layer, 30 cm thick drainage layer, geomembrane liner and 60 cm thick barrier soil layer is recommended because it minimizes cover thickness and would be the most cost-effective design.

NGA-West 2 GMPE average site coefficients for use in earthquake-resistant design

Science.gov (United States)

Borcherdt, Roger D.

2015-01-01

Site coefficients corresponding to those in tables 11.4–1 and 11.4–2 of Minimum Design Loads for Buildings and Other Structures published by the American Society of Civil Engineers (Standard ASCE/SEI 7-10) are derived from four of the Next Generation Attenuation West2 (NGA-W2) Ground-Motion Prediction Equations (GMPEs). The resulting coefficients are compared with those derived by other researchers and those derived from the NGA-West1 database. The derivation of the NGA-W2 average site coefficients provides a simple procedure to update site coefficients with each update in the Maximum Considered Earthquake Response MCER maps. The simple procedure yields average site coefficients consistent with those derived for site-specific design purposes. The NGA-W2 GMPEs provide simple scale factors to reduce conservatism in current simplified design procedures.

Identification of a residue critical for the excision of 3′-blocking ends in apurinic/apyrimidinic endonucleases of the Xth family

Science.gov (United States)

Castillo-Acosta, Víctor M.; Ruiz-Pérez, Luis M.; Yang, Wei; González-Pacanowska, Dolores; Vidal, Antonio E.

2009-01-01

DNA single-strand breaks containing 3′-blocking groups are generated from attack of the sugar backbone by reactive oxygen species or after base excision by DNA glycosylase/apurinic/apyrimidinic (AP) lyases. In human cells, APE1 excises sugar fragments that block the 3′-ends thus facilitating DNA repair synthesis. In Leishmania major, the causal agent of leishmaniasis, the APE1 homolog is the class II AP endonuclease LMAP. Expression of LMAP but not of APE1 reverts the hypersensitivity of a xth nfo repair-deficient Escherichia coli strain to the oxidative compound hydrogen peroxide (H2O2). To identify the residues specifically involved in the repair of oxidative DNA damage, we generated random mutations in the ape1 gene and selected those variants that conferred protection against H2O2. Among the resistant clones, we isolated a mutant in the nuclease domain of APE1 (D70A) with an increased capacity to remove 3′-blocking ends in vitro. D70 of APE1 aligns with A138 of LMAP and mutation of the latter to aspartate significantly reduces its 3′-phosphodiesterase activity. Kinetic analysis shows a novel role of residue D70 in the excision rate of 3′-blocking ends. The functional and structural differences between the parasite and human enzymes probably reflect a divergent molecular evolution of their DNA repair responses to oxidative damage. PMID:19181704

Site characterization plan: Conceptual design report, Volume 1: Chapters 1-3

International Nuclear Information System (INIS)

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R.

1987-09-01

The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases (site and properties of the waste package), design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases

Nuclear depletion of apurinic/apyrimidinic endonuclease 1 (Ape1/Ref-1) is an indicator of energy disruption in neurons.

Science.gov (United States)

Singh, Shilpee; Englander, Ella W

2012-11-01

Apurinic/apyrimidinic endonuclease 1 (Ape1/Ref-1) is a multifunctional protein critical for cellular survival. Its involvement in adaptive survival responses includes key roles in redox sensing, transcriptional regulation, and repair of DNA damage via the base excision repair (BER) pathway. Ape1 is abundant in most cell types and central in integrating the first BER step catalyzed by different DNA glycosylases. BER is the main process for removal of oxidative DNA lesions in postmitotic brain cells, and after ischemic brain injury preservation of Ape1 coincides with neuronal survival, while its loss has been associated with neuronal death. Here, we report that in cultured primary neurons, diminution of cellular ATP by either oligomycin or H(2)O(2) is accompanied by depletion of nuclear Ape1, while other BER proteins are unaffected and retain their nuclear localization under these conditions. Importantly, while H(2)O(2) induces γH2AX phosphorylation, indicative of chromatin rearrangements in response to DNA damage, oligomycin does not. Furthermore, despite comparable diminution of ATP content, H(2)O(2) and oligomycin differentially affect critical parameters of mitochondrial respiration that ultimately determine cellular ATP content. Taken together, our findings demonstrate that in neurons, nuclear compartmentalization of Ape1 depends on ATP and loss of nuclear Ape1 reflects disruption of neuronal energy homeostasis. Energy crisis is a hallmark of stroke and other ischemic/hypoxic brain injuries. In vivo studies have shown that Ape1 deficit precedes neuronal loss in injured brain regions. Thus, our findings bring to light the possibility that energy failure-induced Ape1 depletion triggers neuronal death in ischemic brain injuries. Copyright © 2012 Elsevier Inc. All rights reserved.

Functional mimicry of a discontinuous antigenic site by a designed synthetic peptide

NARCIS (Netherlands)

Villen, J.; Borras, E.; Schaaper, W.M.M.; Meloen, R.H.; Davila, M.; Domingo, E.; Giralt, E.; Andreu, D.

2002-01-01

Functional reproduction of the discontinuous antigenic site D of foot-and-mouth disease virus (FMDV) has been achieved by means of synthetic peptide constructions that integrate each of the three protein loops that define the antigenic site into a single molecule. The site D mimics were designed on

Design Status and Applications of Small reactors without On-site Refuelling

International Nuclear Information System (INIS)

Kuznetsov, V.

2006-01-01

Small reactors without on-site refuelling are the reactors that can operate without reloading and shuffling of fuel for a reasonably long period, consistent with plant economy and considerations of energy security, with no fresh or spent fuel being stored at a site during reactor operation. Such reactors could simplify the implementation of safeguards and provide certain guarantees of sovereignty to those countries that would prefer to lease fuel from a foreign vendor or, perhaps, an international fuel cycle centre. About 30 concepts of such reactors are being analyzed or developed in 6 IAEA Member States. They cover all principle reactor lines: water cooled, fast gas cooled, sodium cooled, lead or lead bismuth cooled and molten salt cooled reactors. An increased refuelling interval could be achieved with reduced core power density, burnable absorbers, or high conversion ratio. The design goals for small reactors without on-site refuelling, inter alia, include: difficult unauthorized access to fuel; design provisions to facilitate the implementation of safeguards; capability to survive all postulated accident scenarios without requiring emergency response in the public domain; economic competitiveness for anticipated market conditions and applications; the capability to achieve higher manufacturing quality through factory mass production, design standardization and common basis for design certification; and a flexibility in siting and applications. Such reactors are often considered in conjunction with fuel or NPP leasing Small reactors without on-site refuelling have many common technology development issues related to the provision of lifetime core operation, economic competitiveness, high level of safety and proliferation resistance. Reestablishment of a practice of licensing by test and establishment of legal provisions and the insurance scheme for a transit of fuel loads or factory fabricated reactors through the territory of a third country are mentioned as

National Ignition Facility subsystem design requirements NIF site improvements SSDR 1.2.1

International Nuclear Information System (INIS)

Kempel, P.; Hands, J.

1996-01-01

This Subsystem Design Requirements (SSDR) document establishes the performance, design, and verification requirements associated with the NIF Project Site at Lawrence Livermore National Laboratory (LLNL) at Livermore, California. It identifies generic design conditions for all NIF Project facilities, including siting requirements associated with natural phenomena, and contains specific requirements for furnishing site-related infrastructure utilities and services to the NIF Project conventional facilities and experimental hardware systems. Three candidate sites were identified as potential locations for the NIF Project. However, LLNL has been identified by DOE as the preferred site because of closely related laser experimentation underway at LLNL, the ability to use existing interrelated infrastructure, and other reasons. Selection of a site other than LLNL will entail the acquisition of site improvements and infrastructure additional to those described in this document. This SSDR addresses only the improvements associated with the NIF Project site located at LLNL, including new work and relocation or demolition of existing facilities that interfere with the construction of new facilities. If the Record of Decision for the PEIS on Stockpile Stewardship and Management were to select another site, this SSDR would be revised to reflect the characteristics of the selected site. Other facilities and infrastructure needed to support operation of the NIF, such as those listed below, are existing and available at the LLNL site, and are not included in this SSDR. Office Building. Target Receiving and Inspection. General Assembly Building. Electro- Mechanical Shop. Warehousing and General Storage. Shipping and Receiving. General Stores. Medical Facilities. Cafeteria services. Service Station and Garage. Fire Station. Security and Badging Services

Site characterization requirements for nuclear-cratering design

International Nuclear Information System (INIS)

Terhune, R.W.; Carlson, R.C.

1977-01-01

A material properties measurement program for the design of large engineering nuclear-excavation projects by computer calculation is presented. Material properties of the site and their relative effect on crater size are analyzed and ordered in relation to their importance in determining the overall cratering efficiency. The measurement program includes both in situ logging and laboratory measurement of core samples, together with the reason for each measurement and its use in the calculations

Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Appendix D, Final report

International Nuclear Information System (INIS)

1992-02-01

This appendix assesses the present conditions and data gathered about the two designated inactive uranium mill tailings sites near Rifle, Colorado, and the proposed disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions

Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Appendix D, Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-02-01

This appendix assesses the present conditions and data gathered about the two designated inactive uranium mill tailings sites near Rifle, Colorado, and the proposed disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

Remedial design of the Fultz Landfill Site, Byesville, Ohio

International Nuclear Information System (INIS)

Rajaram, V.; Riesing, R.; Bloom, T.

1994-01-01

The Fultz Landfill Superfund (Fultz) site is a 30-acre hazardous waste landfill located near Byesville, Ohio. The site is approximately 75 miles east of Columbus and 3 miles southwest of Cambridge, the largest city in Guernsey County, Ohio. The landfill is situated on the north slope of a ridge that overlies abandoned coal mines in the Upper Freeport Coal seam. The north half of the landfill lies in an unreclaimed strip mine in the Upper Freeport Coal seam, where saturated portions of surface mine spoils and natural soils form the ''shallow aquifer''. The south half of the landfill lies 40 to 50 feet (ft.) above an abandoned, flooded deep mine in the same coal seam. The flooded deep mine forms an aquifer referred to as the ''coal mine aquifer''. This paper presents the results of design studies completed by PRC Environmental Management, Inc. (PRC), during 1993, and the remedial design (RD) of the components specified by the US Environmental Protection Agency (EPA) Record of Decision (ROD) for the Fultz site (EPA 1991). The remedy specified in the ROD includes a multilayer landfill cap that is compliant with Resource Conservation and Recovery Act (RCRA) Subtitle C guidelines, a leachate collection and groundwater extraction and treatment system, and stabilizing mine voids underlying the southern portion of the site. Vinyl chloride is the only contaminant exceeding a maximum contaminant limit (MCL) in the coal mine aquifer

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado

International Nuclear Information System (INIS)

1993-07-01

The Slick Rock uranium mill tailings sites are located near the small town of Slick Rock, in San Miguel County, Colorado. There are two designated UMTRA sites at Slick Rock, the Union Carbide (UC) site and the North Continent (NC) site. Both sites are adjacent to the Dolores River. The UC site is approximately 1 mile (mi) [2 kilometers (km)] downstream of the NC site. Contaminated materials cover an estimated 55 acres (ac) [22 hectares (ha)] at the UC site and 12 ac (4.9 ha) at the NC site. The sites contain former mill building concrete foundations, tailings piles, demolition debris, and areas contaminated by windblown and waterborne radioactive materials. The total estimated volume of contaminated materials is approximately 620, 000 cubic yards (yd 3 ) [470,000 cubic meters (m 3 )]. In addition to the contamination at the two processing site areas, four vicinity properties were contaminated. Contamination associated with the UC and NC sites has leached into groundwater

Haplotype-based case-control study on human apurinic/apyrimidinic endonuclease 1/redox effector factor-1 gene and essential hypertension.

Science.gov (United States)

Naganuma, Takahiro; Nakayama, Tomohiro; Sato, Naoyuki; Fu, Zhenyan; Soma, Masayoshi; Yamaguchi, Mai; Shimodaira, Masanori; Aoi, Noriko; Usami, Ron

2010-02-01

Oxidative DNA damage is involved in the pathophysiology of essential hypertension (EH), which is a multifactorial disorder. Apurinic/apyrimidinic endonuclease 1/redox effector factor-1 (APE1/REF-1) is an essential endonuclease in the base excision repair pathway of oxidatively damaged DNA, in addition to having reducing properties that promote the binding of redox-sensitive transcription factors. Blood pressure in APE1/REF-1-knockout mice is reported to be significantly higher than in wild-type mice. The aim of this study was to investigate the relationship between EH and the human APE1/REF-1 gene through a haplotype-based case-control study using single-nucleotide polymorphisms (SNPs). We selected five SNPs in the human APE1/REF-1 gene (rs1760944, rs3136814, rs17111967, rs3136817, and rs1130409), and performed case-control studies in 265 EH patients and 266 age-matched normotensive (NT) subjects. rs17111967 was found to show nonheterogeneity among Japanese subjects. There were no significant differences in the overall distribution of genotypes or alleles for each SNP between EH and NT groups. In the overall distribution of the haplotype-based case-control study constructed based on rs1760944, rs3136817, and rs1130409, the frequency of the G-T-T haplotype was significantly higher in the EH group than in the NT group (2.1% vs. 0.0%, P = 0.001). Multiple logistic regression analysis also revealed significant differences for the G-T-T haplotype, even after adjustment for confounding factors (OR = 8.600, 95% CI: 1.073-68.951, P = 0.043). Based on the present results, the G-T-T haplotype appears to be a genetic marker of EH, and the APE1/REF-1 gene appears to be a susceptibility gene for EH.

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho: Attachment 2, Geology report

International Nuclear Information System (INIS)

1991-09-01

Detailed investigations of geologic, geomorphic, and seismic conditions at the Lowman site in central Idaho were conducted by the Technical Assistance Contractor. The purpose of these investigations was basic site characterization and the identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies (e.g., analyses of the hydrologic regime and liquefaction potential) use this data . The geomorphic analysis is employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65-km (40-mile) radius of the site, provided the basis for estimating seismic design parameters

Site study plan for EDBH [Engineering Design Boreholes] seismic surveys, Deaf Smith County site, Texas: Revision 1

International Nuclear Information System (INIS)

Hume, H.

1987-12-01

This site study plan describes seismic reflection surveys to run north-south and east-west across the Deaf Smith County site, and intersecting near the Engineering Design Boreholes (EDBH). Both conventional and shallow high-resolution surveys will be run. The field program has been designed to acquire subsurface geologic and stratigraphic data to address information/data needs resulting from Federal and State regulations and Repository program requirements. The data acquired by the conventional surveys will be common-depth- point, seismic reflection data optimized for reflection events that indicate geologic structure near the repository horizon. The data will also resolve the basement structure and shallow reflection events up to about the top of the evaporite sequence. Field acquisition includes a testing phase to check/select parameters and a production phase. The field data will be subjected immediately to conventional data processing and interpretation to determine if there are any anamolous structural for stratigraphic conditions that could affect the choice of the EDBH sites. After the EDBH's have been drilled and logged, including vertical seismic profiling, the data will be reprocessed and reinterpreted for detailed structural and stratigraphic information to guide shaft development. The shallow high-resulition seismic reflection lines will be run along the same alignments, but the lines will be shorter and limited to immediate vicinity of the EDBH sites. These lines are planned to detect faults or thick channel sands that may be present at the EDBH sites. 23 refs. , 7 figs., 5 tabs

Remedial design services for Montclair/West Orange and Glen Ridge Superfund sites

International Nuclear Information System (INIS)

Urbaniak, T.F.; Tomiczek, P.W. Jr.

1994-01-01

The Montclair/West Orange and Glen Ridge Superfund Sites are located 12 miles west of New York City in Essex County, New Jersey. The sites are contaminated with waste materials from radium-processing facilities which operated in the area during the early 1900's. The waste materials, containing radium and other radioactive isotopes were placed in three separate landfill sites. Major public health risks are indoor radon gas build-up and indoor/ outdoor gamma radiation. In 1989, the EPA issued a Record of Decision (ROD) which chose excavation and off-site disposal of material as the preferred alternative. The purpose of this presentation is to highlight key elements of the design process for the remedial action at Montclair. Those key elements are as follows: meeting community relations challenges; measuring radioactive contamination; developing plans and specifications; packaging of remedial action contacts; and continually improving both the process and the designs

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Attachment 2, Geology report

International Nuclear Information System (INIS)

1991-12-01

Detailed investigations of geologic, geomorphic, and seismic conditions at the Bodo Canyon disposal site were conducted. The purpose of these investigations was basic site characterization and identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies, such as analyses of hydrologic and liquefaction hazards, used the data developed in these studies. The geomorphic analysis was employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65 kilometer radius of the site, provided the basis for seismic design parameters. The scope of work performed included the following: Compilation and analysis of previous published and unpublished geologic literature and maps; Review of historical and instrumental earthquake data; Review of site-specific subsurface geologic data, including lithologic and geophysical logs of exploratory boreholes advanced in the site area; Photogeologic interpretations of existing conventional aerial photographs; and, Ground reconnaissance and mapping of the site region

How to open & operate a financially successful web site design business

CERN Document Server

Evans, Charlotte

2009-01-01

The Pricing & Ethical Guidelines Handbook published by the Graphic Arts Guild reports that the average cost of designing a Web site for a small corporation can range from 7,750 to 15,000. It is incredibly easy to see the enormous profit potential. Web design businesses can be run part- or full-time and can easily be started in your own home. As such, they are one of the fastest growing segments of the Internet economy. Here is the manual you need to cash in on this highly profitable segment of the industry. This book is a comprehensive and detailed study of the business side of Web site des

Reactor safety under design basis flood condition for inland sites

International Nuclear Information System (INIS)

Hajela, S.; Bajaj, S.S.; Samota, A.; Verma, U.S.P.; Warudkar, A.S.

2002-01-01

Full text: In June 1994, there was an incident of flooding at Kakrapar Atomic Power Station (KAPS) due to combination of heavy rains and mechanical failure in the operation of gates at the adjoining weir. An indepth review of the incident was carried out and a number of flood protection measures were recommended and were implemented at site. As part of this review, a safety analysis was also done to demonstrate reactor safety with a series of failures considered in the flood protection features. For each inland NPP site, as part of design, different flood scenarios are analysed to arrive at design basis flood (DBF) level. This level is estimated based on worst combination of heavy local precipitation, flooding in river, failure of upstream/downstream water control structures

Cloning and characterization of a functional human homolog of Escherichia coli endonuclease III

Science.gov (United States)

Aspinwall, Richard; Rothwell, Dominic G.; Roldan-Arjona, Teresa; Anselmino, Catherine; Ward, Christopher J.; Cheadle, Jeremy P.; Sampson, Julian R.; Lindahl, Tomas; Harris, Peter C.; Hickson, Ian D.

1997-01-01

Repair of oxidative damage to DNA bases is essential to prevent mutations and cell death. Endonuclease III is the major DNA glycosylase activity in Escherichia coli that catalyzes the excision of pyrimidines damaged by ring opening or ring saturation, and it also possesses an associated lyase activity that incises the DNA backbone adjacent to apurinic/apyrimidinic sites. During analysis of the area adjacent to the human tuberous sclerosis gene (TSC2) in chromosome region 16p13.3, we identified a gene, OCTS3, that encodes a 1-kb transcript. Analysis of OCTS3 cDNA clones revealed an open reading frame encoding a predicted protein of 34.3 kDa that shares extensive sequence similarity with E. coli endonuclease III and a related enzyme from Schizosaccharomyces pombe, including a conserved active site region and an iron/sulfur domain. The product of the OCTS3 gene was therefore designated hNTH1 (human endonuclease III homolog 1). The hNTH1 protein was overexpressed in E. coli and purified to apparent homogeneity. The recombinant protein had spectral properties indicative of the presence of an iron/sulfur cluster, and exhibited DNA glycosylase activity on double-stranded polydeoxyribonucleotides containing urea and thymine glycol residues, as well as an apurinic/apyrimidinic lyase activity. Our data indicate that hNTH1 is a structural and functional homolog of E. coli endonuclease III, and that this class of enzymes, for repair of oxidatively damaged pyrimidines in DNA, is highly conserved in evolution from microorganisms to human cells. PMID:8990169

Engineered surface barriers for waste disposal sites: lysimeter facility design and construction

International Nuclear Information System (INIS)

Phillips, S.J.; Ruben, M.S.; Kirkham, R.R.

1988-01-01

A facility to evaluate performance of engineered surface carriers for confinement of buried wastes has been designed, constructed, and operations initiated. The Field Lysimeter Test Facility is located at the US Department of Energy's Hanford Site in Richland, Washington. The facility consists of 18 one-dimensional drainage and weighing lysimeters used to evaluate 7 replicated barrier treatments. Distinct layers of natural earth materials were used to construct layered soil and rock barriers in each lysimeter. These barrier designs are capable in principal of significantly reducing or precluding infiltration of meteoric water through barriers into underlying contaminated zones. This paper summarizes salient facility design and construction features used in testing of the Hanford Site's engineered surface barriers

Linkage between site characterization program and performance and design data needs

International Nuclear Information System (INIS)

Blanchard, M.B.; Dobson, D.C.; Younker, J.L.; Voegele, M.D.

1990-01-01

The basis for identifying site-specific data needs for the Yucca Mountain site was a thorough review and evaluation of the regulatory requirements for a geologic repository. The US Nuclear Regulatory Commission's (NRC) regulation governing disposal of high-level waste in a geologic repository utilizes a multiple barrier approach that includes reliance on both engineered and natural elements. Given an understanding of the regulatory requirements, the next step was to identify the natural features of the site and the components of the engineered barriers considered most likely to make significant contributions to isolation of waste at Yucca Mountain. The intent was to develop a site testing program that focused on understanding those natural site characteristics and processes most likely to contribute to waste isolation; and providing site data necessary to design and assess the performance of engineered barriers. 3 refs., 3 figs

75 FR 54497 - Ocean Dumping; Guam Ocean Dredged Material Disposal Site Designation

Science.gov (United States)

2010-09-08

.... SUMMARY: The EPA is designating the Guam Deep Ocean Disposal Site (G- DODS) as a permanent ocean dredged... administration of ocean disposal permits; (2) development and maintenance of a site monitoring program; (3... include: (1) Regulating quantities and types of material to be disposed, including the time, rates, and...

Nevada test site low-level and mixed waste repository design in the unsaturated zone

International Nuclear Information System (INIS)

Kawamura, T.A.; Warren, D.M.

1989-01-01

The Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) is used for shallow land disposal of Low-Level Radioactive (LLW) and for retrievable disposal of Mixed Wastes (MW) from various Department of Energy (DOE) facilities. The site is situated in southern Nevada, one of the most arid regions of the United States. Design considerations include vadose zone monitoring in lieu of groundwater monitoring, stringent waste acceptance and packaging criteria, a waste examination and real-time radiography facility, and trench design. 4 refs

Three types of children’s informational web sites: an inventory of design conventions

NARCIS (Netherlands)

Jochmann-Mannak, Hanna; Lentz, Leo; Huibers, Theo W.C.; Sanders, Ted

2012-01-01

"Purpose: Research on Web design conventions has an almost exclusive focus on Web design for adults. There is far less knowledge about Web design for children. For the first time, an overview is presented of the current design conventions for children's informational Web sites. Method: In this study

Constructing sites at a large scale - towards new design (education) methods

DEFF Research Database (Denmark)

Braae, Ellen Marie; Tietjen, Anne

2010-01-01

of the design disciplines within the development of our urban landscapes. At the same time, urban and landscape designers are confronted with new methodological problems. Within a strategic transformation perspective the formulation of the design problem or brief becomes an integrated part of the design process......Since the 1990s the regional scale has regained importance in urban and landscape design. In parallel, the focus in design tasks has shifted from master plans for urban extension to strategic urban transformation projects. The current paradigm of planning by projects reinforces the role....... This paper discusses new design (education) methods based on a relational concept of urban sites and design processes using the actor-network-theory as theoretical frame....

Design of an environmental site assessment template for open radioactive site contamination : a radioecological risk approach and case study

International Nuclear Information System (INIS)

Nguyen, T.

2004-01-01

To reduce redundancy, cost, and time, while at the same time ultimately increasing the effectiveness of the radioactive risk management process, a logical framework incorporating risk assessments (human cancer and environmental risks) into the environmental site assessment process was designed for radioactive open site contamination. Risk-based corrective action is becoming an increasingly more acceptable approach for the remediation of contaminated sites. In the past, cleanup goals were usually established without any regard to the risk involved, by mandating remediation goals based solely on maximum contamination levels. Now, a multi-stage environmental site assessment template has been developed on a radioecological approach. The template gives a framework for making environmentally sound decisions based on relevant regulations and guidelines. The first stage involves the comparison of the background screening activity level to the regulated activity level, the second stage involves the use of site-specific information to determine the risk involved with the contamination, and the third stage provides a remediation decision matrix based on results from the first two stages. This environmental site assessment template is unique because it incorporates the modified Canadian National Classification System for radioactive contaminated sites and two different types of risk assessments (human cancer risks and the newly designed ecological risk) into the decision making process. The template was used to assess a radiologically contaminated site at the Canadian Forces Base at Suffield (Alberta) as a case study, and it reaffirms the Department of National Defence's action as appropriate. This particular site is a Class 3, has an overall insignificant human cancer risk ( -6 ) and a low environmental risk, and conforms to all regulated guidelines. Currently, it is restricted and should be left as is, provided that the subsurface is not disturbed. (author)

Geohydrologic aspects for siting and design of low-level radioactive-waste disposal

Science.gov (United States)

Bedinger, M.S.

1989-01-01

The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard as a result of radioactive decay. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by ground water. The unsaturated zone generally is preferred for isolating the waste. Low-level radioactive waste may need to be isolated for 300 to 500 years. Maintenance and monitoring of the repository site are required by Federal regulations for only the first 100 years. Therefore, geohydrology of the repository site needs to provide natural isolation of the waste for the hazardous period following maintenance of the site. Engineering design of the repository needs to be compatible with the natural geohydrologic conditions at the site. Studies at existing commercial and Federal waste-disposal sites provide information on the problems encountered and the basis for establishing siting guidelines for improved isolation of radioactive waste, engineering design of repository structures, and surveillance needs to assess the effectiveness of the repositories and to provide early warning of problems that may require remedial action.Climate directly affects the hydrology of a site and probably is the most important single factor that affects the suitability of a site for shallow-land burial of low-level radioactive waste. Humid and subhumid regions are not well suited for shallow isolation of low-level radioactive waste in the unsaturated zone; arid regions with zero to small infiltration from precipitation, great depths to the water table, and long flow paths to natural discharge areas are naturally well suited to isolation of the waste. The unsaturated zone is preferred for isolation of low-level radioactive waste. The guiding rationale is to minimize contact of water with the waste and to

Radiotracers for per studies of neurotransmitter binding sites: Design considerations

International Nuclear Information System (INIS)

Kilbourn, M.R.

1991-01-01

Neurotransmitter binding sites, such as receptors, neuronal uptake systems, and vesicular uptake systems, are important targets for new radiopharmaceutical design. Selection of potential radioligands can be guided by in vitro laboratory data including such characteristics as selectivity and affinity for specific binding sites. However, development of PET radiotracers for use in vivo must include considerations of in vivo pharmacokinetics and metabolism. Introduction of potential radioligands is further narrowed by the demands of the radiochemical synthesis, which must produce radioligands of high chemical and radiochemical purity and of high specific activity. This paper will review examples of previous and current attempts by radiopharmaceutical chemists to meet these demands for new positron emitter-labeled radioligands for PET studies of a wide array of neurotransmitter binding sites

Evaluation of dynamic properties, local site effects and design ground motions: recent advances

International Nuclear Information System (INIS)

Sitharam, T.G.; Vipin, K.S.; James, Naveen

2011-01-01

Evidences from past earthquakes clearly shows that the damages due to an earthquake and its severity at a site are controlled mainly by three factors i.e., earthquake source and path characteristics, local geological and geotechnical characteristics, structural design and quality of the construction. Seismic ground response at a site is strongly influenced by local geological and soil conditions. The exact information of the geological, geomorphological and geotechnical data along with seismotectonic details are necessary to evaluate the ground response. The geometry of the subsoil structure, the soil type, the lateral discontinuities and the surface topography will also influence the site response at a particular location. In the case of a nuclear power plant, the details obtained from the site investigation will have multiple objectives: (i) for the effective design of the foundation (ii) assessment of site amplification (iii) for liquefaction potential evaluation. Since the seismic effects on the structure depend fully on the site conditions and assessment of site amplification. The first input required in evaluation of geotechnical aspect of seismic hazard is the rock level peak horizontal acceleration (PHA) values. The surface level acceleration values need to be calculated based on the site conditions and site amplification values. This paper discusses various methods for evaluating the site amplification values, dynamic soil properties, different field and laboratory tests required and various site classification schemes. In addition to these aspects, the evaluation of liquefaction potential of the site is also presented. The paper highlights on the latest testing methods to evaluate dynamic properties (shear modulus and damping ratio) of soils and techniques for estimating local site effects. (author)

41 CFR 102-76.20 - What issues must Federal agencies consider in providing site planning and landscape design services?

Science.gov (United States)

2010-07-01

... agencies consider in providing site planning and landscape design services? 102-76.20 Section 102-76.20... What issues must Federal agencies consider in providing site planning and landscape design services? In providing site planning and design services, Federal agencies must— (a) Make the site planning and landscape...

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 2, Appendices D and E: Final report

Energy Technology Data Exchange (ETDEWEB)

1992-02-01

This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

International Nuclear Information System (INIS)

2009-01-01

Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP)

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1994-03-01

The uranium processing site near Naturita, Colorado, is one of 24 inactive uranium mill sites designated to be cleaned up by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), 42 USC section 7901 et seq. Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which describes the proposed remedial action for the Naturita site. An extensive amount of data and supporting information has been generated and evaluated for this remedial action. These data and supporting information are not incorporated into this single document but are included or referenced in the supporting documents. The RAP consists of this RAS and four supporting documents or attachments. This Attachment 2, Geology Report describes the details of geologic, geomorphic, and seismic conditions at the Dry Flats disposal site

Design report for the interim waste containment facility at the Niagara Falls Storage Site

International Nuclear Information System (INIS)

1986-05-01

Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection

Molecular dynamics explorations of active site structure in designed and evolved enzymes.

Science.gov (United States)

Osuna, Sílvia; Jiménez-Osés, Gonzalo; Noey, Elizabeth L; Houk, K N

2015-04-21

This Account describes the use of molecular dynamics (MD) simulations to reveal how mutations alter the structure and organization of enzyme active sites. As proposed by Pauling about 70 years ago and elaborated by many others since then, biocatalysis is efficient when functional groups in the active site of an enzyme are in optimal positions for transition state stabilization. Changes in mechanism and covalent interactions are often critical parts of enzyme catalysis. We describe our explorations of the dynamical preorganization of active sites using MD, studying the fluctuations between active and inactive conformations normally concealed to static crystallography. MD shows how the various arrangements of active site residues influence the free energy of the transition state and relates the populations of the catalytic conformational ensemble to the enzyme activity. This Account is organized around three case studies from our laboratory. We first describe the importance of dynamics in evaluating a series of computationally designed and experimentally evolved enzymes for the Kemp elimination, a popular subject in the enzyme design field. We find that the dynamics of the active site is influenced not only by the original sequence design and subsequent mutations but also by the nature of the ligand present in the active site. In the second example, we show how microsecond MD has been used to uncover the role of remote mutations in the active site dynamics and catalysis of a transesterase, LovD. This enzyme was evolved by Tang at UCLA and Codexis, Inc., and is a useful commercial catalyst for the production of the drug simvastatin. X-ray analysis of inactive and active mutants did not reveal differences in the active sites, but relatively long time scale MD in solution showed that the active site of the wild-type enzyme preorganizes only upon binding of the acyl carrier protein (ACP) that delivers the natural acyl group to the active site. In the absence of bound ACP

The discussion of nuclear power plant's cooling chain design for freezing site

International Nuclear Information System (INIS)

Hu Jian; Yang Ting; Jiang Xulun

2014-01-01

The Component cooling water system (RRI) and Essential service water system (SEC) are composed of Nuclear Power Plant's (NPP) cooling chain, which has its special requirement for freezing site from system design and safety point of view. The feature and difficulty of cooling chain design at freezing condition (when the intake water temperature is below O ℃) are represented. At present, several NPPs are in operation or under construction at freezing site in the world, including Pressurized Water Reactor (PWR) and Canadian Deuterium Uranium reactor (CANDU). By analyzing the thoughts and applicability of different kinds of cooling chain design at freezing site, one solution called 'SEC thermal discharge reflux' is proposed to remove the residual heat from Nuclear Island (NI) into heat sink safely in winter. The solution has been approved by National Nuclear Safety Administration (NNSA) in China and applied in one of CPR NPP in the north of China, which is able to solve several problems compared with the traditional solutions, such as 'Reactor low power operation', 'Reactor start-up for the first time', and 'Changeover of RRI/SEC trains in winter'. The solution is also able to prevent RRI/SEC heat exchanger from icing and avoid low flowrate in SEC pipes. Besides, considering of the economical efficiency, simple operation and control strategy is designed. (authors)

Perceptions of Web Site Design Characteristics: A Malaysian/Australian Comparison.

Science.gov (United States)

Fink, Dieter; Laupase, Ricky

2000-01-01

Compares the perceptions of Malaysians and Australians for four Web site design characteristics--atmospherics, news stories, signs, and products and services--as part of the integrated Internet marketing model. Hypothesizes that the predominant culture is not generalized to another culture, discusses validity and reliability, and suggest further…

Conceptual design analyses for Hanford Site deployable remote spectroscopy systems

International Nuclear Information System (INIS)

Philipp, B.L.; Reich, F.R.

1994-09-01

This document identifies potential remote, NIR spectroscopic waste surface moisture monitoring system design alternatives to be operated inside one of the Hanford Site, high level, nuclear waste storage tanks. Potential tank waste moisture data impacts from the remote NIR signal transfer through high humidity vapor space is evaluated

Central repository for low- and intermediate-level waste (ALMA) conceptual design, siting and safety study

International Nuclear Information System (INIS)

Kjellbert, N.; Haeggblom, H.; Cederstroem, M.; Lundgren, T.

1980-07-01

A generic design, siting and safety study of a proposed repository for low- and intermediate-level waste has been made. Special emphasis has been placed on safety characterostics. The conceptual design and the generic site, on which the study is based, are realistically chosen in accordance with present construction techniques and the existing geohydrological conditions in Sweden. (Auth.)

Study of seismic design bases and site conditions for nuclear power plants

International Nuclear Information System (INIS)

1980-04-01

This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches

Study of seismic design bases and site conditions for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

1980-04-01

This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

Design and implementation of an identification system in construction site safety for proactive accident prevention.

Science.gov (United States)

Yang, Huanjia; Chew, David A S; Wu, Weiwei; Zhou, Zhipeng; Li, Qiming

2012-09-01

Identifying accident precursors using real-time identity information has great potential to improve safety performance in construction industry, which is still suffering from day to day records of accident fatality and injury. Based on the requirements analysis for identifying precursor and the discussion of enabling technology solutions for acquiring and sharing real-time automatic identification information on construction site, this paper proposes an identification system design for proactive accident prevention to improve construction site safety. Firstly, a case study is conducted to analyze the automatic identification requirements for identifying accident precursors in construction site. Results show that it mainly consists of three aspects, namely access control, training and inspection information and operation authority. The system is then designed to fulfill these requirements based on ZigBee enabled wireless sensor network (WSN), radio frequency identification (RFID) technology and an integrated ZigBee RFID sensor network structure. At the same time, an information database is also designed and implemented, which includes 15 tables, 54 queries and several reports and forms. In the end, a demonstration system based on the proposed system design is developed as a proof of concept prototype. The contributions of this study include the requirement analysis and technical design of a real-time identity information tracking solution for proactive accident prevention on construction sites. The technical solution proposed in this paper has a significant importance in improving safety performance on construction sites. Moreover, this study can serve as a reference design for future system integrations where more functions, such as environment monitoring and location tracking, can be added. Copyright © 2011 Elsevier Ltd. All rights reserved.

Design and control strategy for a hybrid green energy system for mobile telecommunication sites

Science.gov (United States)

Okundamiya, Michael S.; Emagbetere, Joy O.; Ogujor, Emmanuel A.

2014-07-01

The rising energy costs and carbon footprint of operating mobile telecommunication sites in the emerging world have increased research interests in green technology. The intermittent nature of most green energy sources creates the problem of designing the optimum configuration for a given location. This study presents the design analysis and control strategy for a cost effective and reliable operation of the hybrid green energy system (HGES) for GSM base transceiver station (BTS) sites in isolated regions. The design constrains the generation and distribution of power to reliably satisfy the energy demand while ensuring safe operation of the system. The overall process control applies the genetic algorithm-based technique for optimal techno-economic sizing of system's components. The process simulation utilized meteorological data for 3 locations (Abuja, Benin City and Sokoto) with varying climatic conditions in Nigeria. Simulation results presented for green GSM BTS sites are discussed and compared with existing approaches.

HTP-OligoDesigner: An Online Primer Design Tool for High-Throughput Gene Cloning and Site-Directed Mutagenesis.

Science.gov (United States)

Camilo, Cesar M; Lima, Gustavo M A; Maluf, Fernando V; Guido, Rafael V C; Polikarpov, Igor

2016-01-01

Following burgeoning genomic and transcriptomic sequencing data, biochemical and molecular biology groups worldwide are implementing high-throughput cloning and mutagenesis facilities in order to obtain a large number of soluble proteins for structural and functional characterization. Since manual primer design can be a time-consuming and error-generating step, particularly when working with hundreds of targets, the automation of primer design process becomes highly desirable. HTP-OligoDesigner was created to provide the scientific community with a simple and intuitive online primer design tool for both laboratory-scale and high-throughput projects of sequence-independent gene cloning and site-directed mutagenesis and a Tm calculator for quick queries.

Conceptual design report for regional low-level waste interim storage site

International Nuclear Information System (INIS)

Bird, M.V.; Thompson, J.D.

1981-08-01

An interim storage site design concept was developed for receiving 100,000 ft 3 low-level waste per year, in the form of solidified wastes in 55-gallon drums with a dose rate of < 200 mrem per hour at contact

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Rifle, Colorado

International Nuclear Information System (INIS)

1990-02-01

This document has been structured to provide a comprehensive understanding of the remedial action proposed for the Rifle sites. That remedial action consists of removing approximately 4,185,000 cubic yards (cy) of tailings and contaminated materials from their current locations, transporting, and stabilizing the tailings material at the Estes Gulch disposal site, approximately six miles north of Rifle. The tailings and contaminated materials are comprised of approximately 597,000 cy from Old Rifle, 3,232,000 cy from New Rifle, and 322,000 cy from vicinity properties and about 34,000 cy from demolition. The remedial action plan includes specific design requirements for the detailed design and construction of the remedial action. An extensive amount of data and supporting information have been generated for this remedial action and cannot all be incorporated into this document. Pertinent information and data are included with reference given to the supporting documents

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1993-08-01

The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (40 CFR 192). The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 designated responsibility to the US Department of Energy (DOE) for assessing the inactive uranium milling sites. The DOE has determined that each assessment shall include information on site characterization, a description of the proposed action, and a summary of the water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards. To achieve compliance with the proposed US Environmental Protection Agency (EPA) groundwater protection standards, the US Department of Energy (DOE) proposes that supplemental standards be applied at the Dry Flats disposal site because of Class III (limited use) groundwater in the uppermost aquifer (the basal sandstone of the Cretaceous Burro Canyon Formation) based on low yield. The proposed remedial action will ensure protection of human health and the environment

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1993-08-01

The uranium processing site near Naturita, Colorado, is one of 24 inactive uranium mill sites designated to be cleaned up by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), Public Law 95-604. Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which serves two purposes. First, it describes the activities that are proposed by the DOE to accomplish remediation and long-term stabilization and control of the radioactive materials at the inactive uranium processing site near Naturita, Colorado. Second, this document and the rest of the RAP, upon concurrence and execution by the DOE, the state of Colorado, and the NRC, become Appendix B of the cooperative agreement between the DOE and the State of Colorado

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Attachment 2, Geology report. Revised final report

Energy Technology Data Exchange (ETDEWEB)

1991-12-01

Detailed investigations of geologic, geomorphic, and seismic conditions at the Bodo Canyon disposal site were conducted. The purpose of these investigations was basic site characterization and identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies, such as analyses of hydrologic and liquefaction hazards, used the data developed in these studies. The geomorphic analysis was employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65 kilometer radius of the site, provided the basis for seismic design parameters. The scope of work performed included the following: Compilation and analysis of previous published and unpublished geologic literature and maps; Review of historical and instrumental earthquake data; Review of site-specific subsurface geologic data, including lithologic and geophysical logs of exploratory boreholes advanced in the site area; Photogeologic interpretations of existing conventional aerial photographs; and, Ground reconnaissance and mapping of the site region.

Comment and response document for the final remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado. Revision 2

International Nuclear Information System (INIS)

1996-05-01

This document for the final remedial action plan and site design has been prepared for US Department of Energy Environmental Restoration Division as part of the Uranium Mill Tailings Remedial Action plan. Comments and responses are included for the site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado

Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

International Nuclear Information System (INIS)

Elder, J.; Graf, J.M.

1984-01-01

DOE Office of Nuclear Safety has sponsored preparation of a guidance document to aid field offices and contractors in their analyses of consequences of postulated major accidents. The guide addresses the requirements of DOE Orders 5480.1A, Chapter V, and 6430.1, including the general requirement that DOE nuclear facilities be sited, designed, and operated in accordance with standards, codes, and guides consistent with those applied to comparable licensed nuclear facilities. The guide includes both philosophical and technical information in the areas of: siting guidelines doses applied to an offsite reference person; consideration also given to an onsite reference person; physical parameters, models, and assumptions to be applied when calculating doses for comparison to siting criteria; and potential accident consequences other than radiological dose to a reference person which might affect siting and major design features of the facility, such as environmental contamination, population dose, and associated public health effects. Recommendations and/or clarifications are provided where this could be done without adding new requirements. In this regard, the guide is considered a valuable aid to the safety analyst, especially where requirements have been subject to inconsistent interpretation or where analysis methods are in transition, such as use of dose model (ICRP 2 or ICRP 30) or use of probabilistic methods of risk analysis in the siting and design of nuclear facilities

Current plans to characterize the design basis ground motion at the Yucca Mountain, Nevada Site

International Nuclear Information System (INIS)

Simecka, W.B.; Grant, T.A.; Voegele, M.D.; Cline, K.M.

1992-01-01

A site at Yucca Mountain Nevada is currently being studied to assess its suitability as a potential host site for the nation's first commercial high level waste repository. The DOE has proposed a new methodology for determining design-basis ground motions that uses both deterministic and probabilistic methods. The role of the deterministic approach is primary. It provides the level of detail needed by design engineers in the characterization of ground motions. The probabilistic approach provides a logical structured procedure for integrating the range of possible earthquakes that contribute to the ground motion hazard at the site. In addition, probabilistic methods will be used as needed to provide input for the assessment of long-term repository performance. This paper discusses the local tectonic environment, potential seismic sources and their associated displacements and ground motions. It also discusses the approach to assessing the design basis earthquake for the surface and underground facilities, as well as selected examples of the use of this type of information in design activities

Are Biophilic-Designed Site Office Buildings Linked to Health Benefits and High Performing Occupants?

Directory of Open Access Journals (Sweden)

Tonia Gray

2014-11-01

Full Text Available This paper discusses the first phase of a longitudinal study underway in Australia to ascertain the broad health benefits of specific types of biophilic design for workers in a building site office. A bespoke site design was formulated to include open plan workspace, natural lighting, ventilation, significant plants, prospect and views, recycled materials and use of non-synthetic materials. Initial data in the first three months was gathered from a series of demographic questions and from interviews and observations of site workers. Preliminary data indicates a strong positive effect from incorporating aspects of biophilic design to boost productivity, ameliorate stress, enhance well-being, foster a collaborative work environment and promote workplace satisfaction, thus contributing towards a high performance workspace. The longitudinal study spanning over two years will track human-plant interactions in a biophilic influenced space, whilst also assessing the concomitant cognitive, social, psychological and physical health benefits for workers.

Estimating open population site occupancy from presence-absence data lacking the robust design.

Science.gov (United States)

Dail, D; Madsen, L

2013-03-01

Many animal monitoring studies seek to estimate the proportion of a study area occupied by a target population. The study area is divided into spatially distinct sites where the detected presence or absence of the population is recorded, and this is repeated in time for multiple seasons. However, when occupied sites are detected with probability p Ecology 84, 2200-2207) developed a multiseason model for estimating seasonal site occupancy (ψt ) while accounting for unknown p. Their model performs well when observations are collected according to the robust design, where multiple sampling occasions occur during each season; the repeated sampling aids in the estimation p. However, their model does not perform as well when the robust design is lacking. In this paper, we propose an alternative likelihood model that yields improved seasonal estimates of p and Ψt in the absence of the robust design. We construct the marginal likelihood of the observed data by conditioning on, and summing out, the latent number of occupied sites during each season. A simulation study shows that in cases without the robust design, the proposed model estimates p with less bias than the MacKenzie et al. model and hence improves the estimates of Ψt . We apply both models to a data set consisting of repeated presence-absence observations of American robins (Turdus migratorius) with yearly survey periods. The two models are compared to a third estimator available when the repeated counts (from the same study) are considered, with the proposed model yielding estimates of Ψt closest to estimates from the point count model. Copyright © 2013, The International Biometric Society.

Design methodology for the physical protection upgrade rule requirements for fixed sites. Technical report

International Nuclear Information System (INIS)

Evans, L.J. Jr.; Allen, T.

1980-06-01

This Design Methodology document aids the licensee in understanding how the fixed site requirements of the Physical Protection Upgrade Rule affect the design of physical protection systems for fuel processing plants, fuel manufacturing plants, or other fixed site special nuclear material operations involving possession or use of formula quantities of strategic special nuclear material. The document consists of three major elements: Logic Trees, Safeguards Jobs and Component Matrices, and Effectiveness Test Questionnaires. The work is based upon a previous study conducted by Sandia Laboratories for the Nuclear Regulatory Commission

Comments and responses on the Remedial Action Plan and site design for stabilization of the Inactive Uranium Mill Tailings Site, Grand Junction, Colorado. Revision 1

International Nuclear Information System (INIS)

1994-01-01

This report contains information concerning public comments and responses on the remedial action plan and site design for stabilization of the inactive uranium mill tailings site in Grand Junction, Colorado

Review and comment on the US Department of Energy Site Characterization Plan Conceptual Design report

International Nuclear Information System (INIS)

1988-10-01

The ''Site Characterization Plan Conceptual Design Report,'' as prepared by the United States Department of Energy and its contractors, depicts the conceptual designs being proposed for the Yucca Mountain, Nevada High-Level Waste Repository. Much of the report is comprised of designs based on large assumptions that lead to inconclusiveness in terms of technical integrity and reasonableness. As a result, the likely success of the designs proposed within the report is highly questionable from a technical and even constructibility standpoint. Grave deficiencies have been found throughout the report ranging from the over-simplification of the geologic and geohydrologic setting to the incorrect determination of the repository horizon's host rock strength. All of these deficiencies found within the report relate directly to the probable outcome of the site characterization of Yucca Mountain and the possible design and construction of a high-level waste repository at the site. It does not appear that a concerted effort has been put forth to develop many of the concepts within the report to a reasonable level of engineering and scientific integrity that would be suitable to meet the needs of and provide the results to the Nation's High-Level Waste Program

Synthesis and proton-NMR studies of oligonucleotides containing an apurinic (AP) site

International Nuclear Information System (INIS)

Raap, J.; Dreef, C.E.; van der Marel, G.A.; van Boom, J.H.; Hilbers, C.W.

1987-01-01

In order to elucidate the conformational properties of base-deleted oligodeoxyribonucleotides, the molecules d-CpS(pCpG)n (n = 1,2; S = sugar) were synthesized by the phosphotriester method and characterized by 1H-NMR spectroscopy. Complete assignment of all non-exchangeable proton resonances of both compounds was obtained by 1D- and 2D-NMR techniques. In combination with computer simulation, these spectra yielded proton-proton and proton-phosphorus coupling constants of high accuracy. These data provide valuable information about the sugar and the backbone conformation. It appears that d-Cp1Sp2Cp3G4 does not form a duplex under any of the conditions studied. On the contrary, the base-deleted hexamer d-Cp1Sp2Cp3Gp4Cp5G6 occurs as a right-handed' staggered' DNA duplex at 280 K: the core of this duplex is formed by the residues C(3)-G(6); two 'dangling' residues C(1) and S(2) are located at the two 5'-ends of the duplex. The assignment of the corresponding imino proton resonances for [d-CpS(pCpG)2]2 was based on their thermal behavior: the line broadening of these resonances was studied as a function of temperature. The chemical shift and the number of imino proton resonances accord well with the number and type of Watson-Crick base pairs which can be formed in the staggered duplex described above. Thermodynamic parameters of duplex formation were obtained from an analysis of the chemical shift versus temperature profiles of aromatic base and H-1' protons. It is suggested that the cytosine ring of C(1) stacks, at least part of the time, with the guanine ring on the nucleotide residue, G(6), situated in the complementary strand. The binding of Lys-Trp-Lys to [d-CpS(pCpG)2]2 as well as to [d-CpGpCpG]1 was investigated

Early Site Permit Demonstration Program: Station design alternatives report

International Nuclear Information System (INIS)

1993-03-01

This report provides the results of investigating the basis for including Station Design Alternatives (SDAs) in the regulatory guidance given for nuclear plant environmental reports (ERs), explains approaches or processes for evaluating SDAs at the early site permit (ESP) stage, and applies one of the processes to each of the ten systems or subsystems considered as SDAS. The key objective o this report s to demonstrate an adequate examination of alternatives can be performed without the extensive development f design data. The report discusses the Composite Suitability Approach and the Established Cutoff Approach in evaluating station design alternatives and selects one of these approaches to evaluate alternatives for each of the plant or station that were considered. Four types of ALWRs have been considered due to the availability of extensive plant data: System 80+, AP600, Advanced Boiling Reactor (ABWR), and Simplified Boiling Water Reactor (SBWR). This report demonstrates the feasibility of evaluating station design alternatives when reactor design detail has not been determined, quantitatively compares the potential ental impacts of alternatives, and focuses the ultimate selection of a alternative on cost and applicant-specific factors. The range of alternatives system is deliberately limited to a reasonable number to demonstrate the or to the three most commonly used at operating plants

Methodology applied in Cuba for siting, designing, and building a radioactive waste repository under safety conditions

International Nuclear Information System (INIS)

Orbera, L.; Peralta, J.L.; Franklin, R.; Gil, R.; Chales, G.; Rodriguez, A.

1993-01-01

The work presents the methodology used in Cuba for siting, designing, and building a radioactive waste repository safely. This methodology covers both the technical and socio-economic factors, as well as those of design and construction so as to have a safe siting for this kind of repository under Cuba especial condition. Applying this methodology will results in a safe repository

Site characterization plan: Conceptual design report, Volume 2: Chapters 4-9: Nevada Nuclear Waste Storage Investigations Project

International Nuclear Information System (INIS)

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R.

1987-09-01

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases (site and properties of the waste package), design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. 147 refs., 145 figs., 83 tabs

Development of a design basis tornado and structural design criteria for the Nevada Test Site, Nevada. Final report

International Nuclear Information System (INIS)

McDonald, J.R.; Minor, J.E.; Mehta, K.C.

1975-06-01

In order to evaluate the ability of critical facilities at the Nevada Test Site to withstand the possible damaging effects of extreme winds and tornadoes, parameters for the effects of tornadoes and extreme winds and structural design criteria for the design and evaluation of structures were developed. The meteorological investigations conducted are summarized, and techniques used for developing the combined tornado and extreme wind risk model are discussed. The guidelines for structural design include methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from wind-driven missiles. Calculations for determining the design loads for an example structure are included

Seismic site evaluation practice and seismic design guide for NPP in Continent of China

Energy Technology Data Exchange (ETDEWEB)

Yuxian, Hu [State Seismological Bureau, Beijing, BJ (China). Inst. of Geophysics

1997-03-01

Energy resources, seismicity, NPP and related regulations of the Continent of China are briefly introduced in the beginning and two codes related to the seismic design of NPP, one on siting and another on design, are discussed in some detail. The one on siting is an official code of the State Seismological Bureau, which specifies the seismic safety evaluation requirements of various kinds of structures, from the most critic and important structures such as NPP to ordinary buildings, and including also engineering works in big cities. The one on seismic design of NPP is a draft subjected to publication now, which will be an official national code. The first one is somewhat unique but the second one is quite similar to those in the world. (author)

Seismic site evaluation practice and seismic design guide for NPP in Continent of China

International Nuclear Information System (INIS)

Hu Yuxian

1997-01-01

Energy resources, seismicity, NPP and related regulations of the Continent of China are briefly introduced in the beginning and two codes related to the seismic design of NPP, one on siting and another on design, are discussed in some detail. The one on siting is an official code of the State Seismological Bureau, which specifies the seismic safety evaluation requirements of various kinds of structures, from the most critic and important structures such as NPP to ordinary buildings, and including also engineering works in big cities. The one on seismic design of NPP is a draft subjected to publication now, which will be an official national code. The first one is somewhat unique but the second one is quite similar to those in the world. (author)

Aerosol measurements at the Southern Great Plains Site: Design and surface installation

Energy Technology Data Exchange (ETDEWEB)

Leifer, R.; Knuth, R.H.; Guggenheim, S.F.; Albert, B. [Department of Energy, New York, NY (United States)

1996-04-01

To impropve the predictive capabilities of the Atmospheric Radiation Measurements (ARM) program radiation models, measurements of awserosol size distributions, condensation particle concentrations, aerosol scattering coefficients at a number of wavelenghts, and the aerosol absorption coefficients are needed at the Southern Great Plains (SGP) site. Alos, continuous measurements of ozone concnetrations are needed for model validation. The environmental Measuremenr Laboratory (EMK) has the responsibility to establish the surface aerosol measurements program at the SGP site. EML has designed a special sampling manifold.

Study of site layout in the Rokkasho site

International Nuclear Information System (INIS)

Sato, Kazuyoshi; Tamura, Kousaku; Yagenji, Akira; Sekiya, Shigeki; Takahashi, Hideo; Neyatani, Yuzuru; Uehara, Masaharu; Motohashi, Keiichi; Hashimoto, Masayoshi; Ogino, Shunji; Nagamatsu, Nobuhide

2006-03-01

The Final Design Report (FDR) of the International Thermonuclear Experimental Reactor (ITER) was published on July 2001 as a summary of the Engineering Design Activity (EDA). After the EDA, site dependent design has been investigated for the invitation of ITER toward Rokkasho Site (Iyasakadai area) in Aomori prefecture. This report describes the results of site layout of major buildings and structures of ITER in the Rokkasho-Site. The data of the ground near the site and the results of site dependent design in Japan were applied to this study. Through this study, the most appropriate site layout has been constructed with satisfaction of following conditions. (1) Bedrock level at the tokamak complex building is relatively high and it can be reduced the cost of excavation and foundation work. (2) Total amount of excavation soil for site preparation is minimized and the flexibility of the layout is ensured with flat ground level. (3) Accessibility of human and equipments, reduction of noise and vibration to the environment can be obtained. Total length of ducts and piping between buildings in site is minimized. (author)

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Falls City, Texas

International Nuclear Information System (INIS)

Chernoff, A.R.; Lacker, D.K.

1992-09-01

The uranium processing site near Falls City, Texas, was one of 24 inactive uranium mill sites designated to be remediated by the US Department of Energy (DOE) under Title I of the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). The RAP, which includes this summary remedial action selection report (RAS), serves a two-fold purpose. First, it describes the activities proposed by the DOE to accomplish long-term stabilization and control of the residual radioactive materials at the inactive uranium processing site near Falls City, Texas. Second, this document and the remainder of the RAP, upon concurrence and execution by the DOE, the State of Texas, and the NRC, becomes Appendix B of the Cooperative Agreement between the DOE and the State of Texas

Seismic design of circular-section concrete-lined underground openings: Preclosure performance considerations for the Yucca Mountain Site

International Nuclear Information System (INIS)

Richardson, A.M.; Blejwas, T.E.

1992-01-01

Yucca Mountain, the potential site of a repository for high-level radioactive waste, is situated in a region of natural and man-made seismicity. Underground openings excavated at this site must be designed for worker safety in the seismic environment anticipated for the preclosure period. This includes accesses developed for site characterization regardless of the ultimate outcome of the repository siting process. Experience with both civil and mining structures has shown that underground openings are much more resistant to seismic effects than surface structures, and that even severe dynamic strains can usually be accommodated with proper design. This paper discusses the design and performance of lined openings in the seismic environment of the potential site. The types and ranges of possible ground motions (seismic loads) are briefly discussed. Relevant historical records of underground opening performance during seismic loading are reviewed. Simple analytical methods of predicting liner performance under combined in situ, thermal, and seismic loading are presented, and results of calculations are discussed in the context of realistic performance requirements for concrete-lined openings for the preclosure period. Design features that will enhance liner stability and mitigate the impact of the potential seismic load are reviewed. The paper is limited to preclosure performance concerns involving worker safety because present decommissioning plans specify maintaining the option for liner removal at seal locations, thus decoupling liner design from repository postclosure performance issues

GEOTECHNICAL DESIGN OF SOLID WASTE LANDFILL SITES

Directory of Open Access Journals (Sweden)

Suat AKBULUT

2003-02-01

Full Text Available Solid waste landfills are important engineering structures for protection of wastes, decrease of environmental pollution, and especially prevention of soil and water pollution. Solid wastes should conveniently be maintained in landfill areas to control environmental pollution caused by waste disposals. Until the middle of this century clay liners were used for maintenance of waste disposal, but it was observed that these liner systems were insufficient. Today thinner and less permeable liner systems are constructed by using synthetic materials. In this study, by evaluating the waste landfills, site assessment of landfills and construction of natural and synthetic liner systems were summarized respectively, and especially the design properties of these systems were examined intensively. Also, leachate collection and removal facilities, landfill gas collection unites, and final cover unites were evaluated in a detailed way.

Risk assessment data bank design at the Savannah River Site

International Nuclear Information System (INIS)

Townsend, C.S.; Johnson, K.B.

1992-01-01

The Savannah River Site has designed and implemented a database system containing a series of compilations of incidents used primarily for risk assessment. Four databases have been designed and implemented using advanced database management system computer software. These databases exist for reprocessing, fuel fabrication, waste management, and the Savannah River Technology Center. They are combined into one system caged the Risk Assessment Methodology (RAM) Fault Tree Data Banks. This paper will discuss the logical design of the data, the menus, and the operating platform. Built-in updating features, such as batch and on-line data entry; data validation methods; automatic update features; and expert system programs, will also be discussed. User functions, such as on-line search/view/report and statistical functions, will be presented. Security features and backup and recovery methods will also be covered

Catalysis by Design: Well-Defined Single-Site Heterogeneous Catalysts

KAUST Repository

Pelletier, Jeremie

2016-03-09

ConspectusHeterogeneous catalysis, a field important industrially and scientifically, is increasingly seeking and refining strategies to render itself more predictable. The main issue is due to the nature and the population of catalytically active sites. Their number is generally low to very low, their "acid strengths" or " redox properties" are not homogeneous, and the material may display related yet inactive sites on the same material. In many heterogeneous catalysts, the discovery of a structure-activity reationship is at best challenging. One possible solution is to generate single-site catalysts in which most, if not all, of the sites are structurally identical. Within this context and using the right tools, the catalyst structure can be designed and well-defined, to reach a molecular understanding. It is then feasible to understand the structure-activity relationship and to develop predictable heterogeneous catalysis. Single-site well-defined heterogeneous catalysts can be prepared using concepts and tools of surface organometallic chemistry (SOMC). This approach operates by reacting organometallic compounds with surfaces of highly divided oxides (or of metal nanoparticles). This strategy has a solid track record to reveal structure-activity relationship to the extent that it is becoming now quite predictable. Almost all elements of the periodical table have been grafted on surfaces of oxides (from simple oxides such as silica or alumina to more sophisticated materials regarding composition or porosity).Considering catalytic hydrocarbon transformations, heterogeneous catalysis outcome may now be predicted based on existing mechanistic proposals and the rules of molecular chemistry (organometallic, organic) associated with some concepts of surface sciences. A thorough characterization of the grafted metal centers must be carried out using tools spanning from molecular organometallic or surface chemistry. By selection of the metal, its ligand set, and the

Evaluation of E-Learning Web Sites Using Fuzzy Axiomatic Design Based Approach

Directory of Open Access Journals (Sweden)

2010-04-01

Full Text Available High quality web site has been generally recognized as a critical enabler to conduct online business. Numerous studies exist in the literature to measure the business performance in relation to web site quality. In this paper, an axiomatic design based approach for fuzzy group decision making is adopted to evaluate the quality of e-learning web sites. Another multi-criteria decision making technique, namely fuzzy TOPSIS, is applied in order to validate the outcome. The methodology proposed in this paper has the advantage of incorporating requirements and enabling reductions in the problem size, as compared to fuzzy TOPSIS. A case study focusing on Turkish e-learning websites is presented, and based on the empirical findings, managerial implications and recommendations for future research are offered.

Site selection and design basis of the National Disposal Facility for LILW. Geological and engineering barriers

International Nuclear Information System (INIS)

Boyanov, S.

2010-01-01

Content of the presentation: Site selection; Characteristics of the “Radiana” site (location, geological structure, physical and mechanical properties, hydro-geological conditions); Design basis of the Disposal Facility; Migration analysis; Safety assessment approach

Development of a design basis tornado and structural design criteria for Lawrence Livermore Laboratory's Site 300

International Nuclear Information System (INIS)

McDonald, J.R.; Minor, J.E.; Mehta, K.C.

1975-11-01

Criteria are prescribed and guidance is provided for professional personnel who are involved with the evaluation of existing buildings and facilities at Site 300 near Livermore, California to resist the possible effects of extreme winds and tornadoes. The development of parameters for the effects of tornadoes and extreme winds and guidelines for evaluation and design of structures are presented. The investigations conducted are summarized and the techniques used for arriving at the combined tornado and extreme wind risk model are discussed. The guidelines for structural design methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from missiles are also presented

Design and implementation of a computer based site operations log for the ARM Program

International Nuclear Information System (INIS)

Tichler, J.L.; Bernstein, H.J.; Bobrowski, S.F.; Melton, R.B.; Campbell, A.P.; Edwards, D.M.; Kanciruk, P.; Singley, P.T.

1992-01-01

The Atmospheric Radiation Measurement (ARM) Program is a Department of Energy (DOE) research effort to reduce the uncertainties found in general circulation and other models due to the effects of clouds and solar radiation. ARM will provide an experimental testbed for the study of important atmospheric effects, particularly cloud and radiative processes, and testing of parameterizations of the processes for use in atmospheric models. The design of the testbed known as the Clouds and Radiation Testbed (CART), calls for five, long-term field data collection sites. The first site, located in the Southern Great Plains (SGP) in Lamont, OK began operation in the spring of 1992. The CART Data Environment (CDE) is the element of the testbed which acquires the basic observations from the instruments and processes them to meet the ARM requirements. A formal design was used to develop a description of the logical requirements for the CDE. This paper discusses the design and prototype implementation of a part of the CDE known as the site operations log, which records metadata defining the environment within which the data produced by the instruments is collected

The design on high slope stabilization in waste rock sites of uranium mines

International Nuclear Information System (INIS)

Liu Taoan; Zhou Xinghuo; Liu Jia

2005-01-01

Design methods, reinforcement measures, and flood control measures concerning high slope stabilization in harnessing waste rock site are described in brief according to some examples of two uranium mines in Hunan province. (authors)

Custom-Designed Molecular Scissors for Site-Specific Manipulation of the Plant and Mammalian Genomes

Science.gov (United States)

Kandavelou, Karthikeyan; Chandrasegaran, Srinivasan

Zinc finger nucleases (ZFNs) are custom-designed molecular scissors, engineered to cut at specific DNA sequences. ZFNs combine the zinc finger proteins (ZFPs) with the nonspecific cleavage domain of the FokI restriction enzyme. The DNA-binding specificity of ZFNs can be easily altered experimentally. This easy manipulation of the ZFN recognition specificity enables one to deliver a targeted double-strand break (DSB) to a genome. The targeted DSB stimulates local gene targeting by several orders of magnitude at that specific cut site via homologous recombination (HR). Thus, ZFNs have become an important experimental tool to make site-specific and permanent alterations to genomes of not only plants and mammals but also of many other organisms. Engineering of custom ZFNs involves many steps. The first step is to identify a ZFN site at or near the chosen chromosomal target within the genome to which ZFNs will bind and cut. The second step is to design and/or select various ZFP combinations that will bind to the chosen target site with high specificity and affinity. The DNA coding sequence for the designed ZFPs are then assembled by polymerase chain reaction (PCR) using oligonucleotides. The third step is to fuse the ZFP constructs to the FokI cleavage domain. The ZFNs are then expressed as proteins by using the rabbit reticulocyte in vitro transcription/translation system and the protein products assayed for their DNA cleavage specificity.

Subsurface moisture regimes and tracer movement under two types of trench-cap designs for shallow land burial sites

International Nuclear Information System (INIS)

Perkins, B.A.; Cokal, E.J.

1986-03-01

The Los Alamos work has focused on proper design of shallow land burial (SLB) sites in arid and semiarid regions and on applying corrective measures to existing sites. One of the most important design features affecting the probability of movement of radionuclides in SLB sites is the type of trench cap placed over the waste. The cap influences such interdependent parameters as erosion, water infiltration and percolation, and biointrusion. To obtain experimental data for arid and semiarid sites, two different designs of trench caps, one with topsoil underlain with a cobble/gravel biobarrier and one with topsoil underlain with crushed tuff, were compared with respect to (1) seasonal changes in volumetric soil water content, and (2) downward migration of tracers emplaced directly below each type of trench cap. The causes for the large differences in concentrations found in this experiment need to be investigated further. Problems in environmental modeling and monitoring of arid and semiarid SLB sites because of heterogeneities in the soil profiles and their implications for SLB waste management need to be better understood. More work in trench-cap design and its influence on the many pathways available for mobilization is needed

Modifications to the remedial action plan and site design for stabilization of the inactive Uranium Mill Tailings Site at Green River, Utah

International Nuclear Information System (INIS)

1994-09-01

Modifications to the water resources protection strategy detailed in the remedial action plan for the Green River, Utah, disposal site are presented. The modifications are based on new information, including ground water quality data collected after remedial action was completed and on a revised assessment of disposal cell design features, surface conditions, and site hydrogeology. The modifications will result in compliance with the U.S. EPA proposed ground water standards (52 FR 36000 (1987))

THE DESIGN AND IMPLEMETATION OF THE RESEARCH CENTER FOR AERONAUTICS AND SPACE WEB SITE

Directory of Open Access Journals (Sweden)

LEHADUS Daniel

2010-11-01

Full Text Available This paper presents some elements and principles commonly used in web design. It’s addressed to anyone with an interest in developing their skills as a visual communicator, anyone who wants to learn the basics of graphical design, so they can develop their artistic skills and make more powerful and effective web sites.

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Tuba City, Arizona

International Nuclear Information System (INIS)

1989-08-01

This Remedial Action Plan (RAP) has been developed to serve a threefold purpose. It presents the series of activities which are proposed by the US Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at the inactive uranium processing site near Tuba City, Arizona. It provides a characterization of the present conditions of the site. It also serves to document the concurrence of the Navajo Nation, the Hopi Tribe, US Bureau of Indian Affairs (BIA), and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by DOE, the Navajo Nation, and the Hopi Tribe, and concurrence by NRC, becomes Appendix B of the Cooperative Agreement. Following the introduction, contents are as follows: Section 2.0 presents the EPA standards, including a discussion of their objectives. Section 3.0 summarizes the present site characteristics and provides a definition of site-specific problems. Section 4.0 is the site design for the proposed action. Section 5.0 summarizes the plan for ensuring environmental, health, and safety protection for the surrounding community and the on-site workers. Section 6.0 presents a detailed listing of the responsibilities of the project participants. Section 7.0 describes the features of the long-term surveillance and maintenance plan. Section 8.0 presents the quality assurance aspects of the project. Section 9.0 documents the ongoing activities to keep the public informed and participating in the project

Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

International Nuclear Information System (INIS)

1993-01-01

This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical ampersand Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties

That Was Then, This Is Now: Replacing the Mobile-Optimized Site with Responsive Design

Directory of Open Access Journals (Sweden)

Laurie M. Bridges

2013-12-01

Full Text Available As mobile technologies continue to evolve, libraries seek sustainable ways to keep up with these changes and to best serve our users.  Previous library mobile usability research has examined tasks users predict they might be likely to perform, but little is known about what users actually do on a mobile-optimized library site.  This research used a combination of survey methodology and web analytics to examine what tasks users actually carry out on a library mobile site.  The results indicate that users perform an array of passive and active tasks and do not want content choices to be limited on mobile devices.  Responsive design is described as a long-term solution for addressing both designers and users’ needs.

Siting, design and construction of underground repositories for radioactive wastes

International Nuclear Information System (INIS)

1986-01-01

The objectives of the Symposium were to provide a forum for exchange of information internationally on the various scientific, technological, engineering and safety bases for the siting, design and construction of underground repositories, and to highlight current important issues and identify possible approaches. Forty-nine papers were presented, covering general approaches and regulatory aspects, disposal in shallow ground and rock cavities, disposal in deep geological formations and safety assessments related to the subject of the Symposium. Separate abstracts were prepared for each of these papers

Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings Site, Maybell, Colorado. Remedial action selection report: Attachment 2, Geology report, Final

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

The Maybell uranium mill tailings site is 25 miles (mi) (40 kilometers [km]) west of the town of Craig, Colorado, in Moffat County, in the northwestern part of the state. The unincorporated town of Maybell is 5 road mi (8 km) southwest of the site. The designated site covers approximately 110 acres (ac) (45 hectares [ha]) and consists of a concave-shaped tailings pile and rubble from the demolition of the mill buildings buried in the former mill area. Contaminated materials at the Maybell processing site include the tailings pile, which has an average depth of 20 feet (ft) (6 meters [m]) and contains 2.8 million cubic yards (yd{sup 3}) (2.1 million cubic meters [m{sup 3}]) of tailings. The former mill processing area is on the north side of the site and contains 20,000 yd{sup 3} (15,000 m{sup 3}) of contaminated demolition debris. Off-pile contamination is present and includes areas adjacent to the tailings pile, as well as contamination dispersed by wind and surface water flow. The volume of off-pile contamination to be placed in the disposal cell is 550,000 yd{sup 3} (420,000 m{sup 3}). The total volume of contaminated materials to be disposed of as part of the remedial action is estimated to be 3.37 million yd{sup 3} (2.58 million m{sup 3}). Information presented in this Final Remedial Action Plan (RAP) and referenced in supporting documents represents the current disposal cell design features and ground water compliance strategy proposed by the US Department of Energy (DOE) for the Maybell, Colorado, tailings site. Both the disposal cell design and the ground water compliance strategy have changed from those proposed prior to the preliminary final RAP document as a result of prudent site-specific technical evaluations.

Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings Site, Maybell, Colorado. Remedial action selection report: Attachment 2, Geology report, Final

International Nuclear Information System (INIS)

1994-06-01

The Maybell uranium mill tailings site is 25 miles (mi) (40 kilometers [km]) west of the town of Craig, Colorado, in Moffat County, in the northwestern part of the state. The unincorporated town of Maybell is 5 road mi (8 km) southwest of the site. The designated site covers approximately 110 acres (ac) (45 hectares [ha]) and consists of a concave-shaped tailings pile and rubble from the demolition of the mill buildings buried in the former mill area. Contaminated materials at the Maybell processing site include the tailings pile, which has an average depth of 20 feet (ft) (6 meters [m]) and contains 2.8 million cubic yards (yd 3 ) (2.1 million cubic meters [m 3 ]) of tailings. The former mill processing area is on the north side of the site and contains 20,000 yd 3 (15,000 m 3 ) of contaminated demolition debris. Off-pile contamination is present and includes areas adjacent to the tailings pile, as well as contamination dispersed by wind and surface water flow. The volume of off-pile contamination to be placed in the disposal cell is 550,000 yd 3 (420,000 m 3 ). The total volume of contaminated materials to be disposed of as part of the remedial action is estimated to be 3.37 million yd 3 (2.58 million m 3 ). Information presented in this Final Remedial Action Plan (RAP) and referenced in supporting documents represents the current disposal cell design features and ground water compliance strategy proposed by the US Department of Energy (DOE) for the Maybell, Colorado, tailings site. Both the disposal cell design and the ground water compliance strategy have changed from those proposed prior to the preliminary final RAP document as a result of prudent site-specific technical evaluations

The Role of Virtual Reference in Library Web Site Design: A Qualitative Source for Usage Data

Science.gov (United States)

Powers, Amanda Clay; Shedd, Julie; Hill, Clay

2011-01-01

Gathering qualitative information about usage behavior of library Web sites is a time-consuming process requiring the active participation of patron communities. Libraries that collect virtual reference transcripts, however, hold valuable data regarding how the library Web site is used that could benefit Web designers. An analysis of virtual…

Siting, design and cost of shallow land burial facilities in northern New England. Volume 1

International Nuclear Information System (INIS)

1985-05-01

This study investigated the technical feasibility and cost of shallow land burial (SLB) as one low-level radioactive waste disposal option for Maine and the northern New England states of Maine, New Hampshire, and Vermont. The results are presented in five chapters addressing the licensing process for an SLB facility, the siting process, the engineering design, the cost of disposal, and the cost of transportation. Chapter 2 reviews the Federal and State licensing processes and requirements for development of an SLB facility. Included in this discussion are the stages in the life cycle of SLB facility. Chapter 3 provides site selection criteria for Maine and presents a proposed site selection methodology. The site selection criteria are defined and the reasoning behind their selection is explained. Chapter 4 discusses SLB trench and facility designs and costs. To accommodate different waste volume scenarios, differently sized facilities are discussed, representing Maine going-it-alone and a northern New England compact. Designs and costs of scenarios including nuclear power plant decommissioning wastes are also discussed. Cost estimates of licensing, facility construction, operation, closure, and post closure care are presented for the different waste volume scenarios. Chapter 5 presents estimates of what it would cost LLW generators to dispose of their waste in a Maine-only or a northern New England shallow land burial facility. The reliability of the estimates and their sensitivity to changes in waste volume are also discussed. Chapter 6 examines transportation costs

Examination of CRISPR/Cas9 design tools and the effect of target site accessibility on Cas9 activity.

Science.gov (United States)

Lee, Ciaran M; Davis, Timothy H; Bao, Gang

2018-04-01

What is the topic of this review? In this review, we analyse the performance of recently described tools for CRISPR/Cas9 guide RNA design, in particular, design tools that predict CRISPR/Cas9 activity. What advances does it highlight? Recently, many tools designed to predict CRISPR/Cas9 activity have been reported. However, the majority of these tools lack experimental validation. Our analyses indicate that these tools have poor predictive power. Our preliminary results suggest that target site accessibility should be considered in order to develop better guide RNA design tools with improved predictive power. The recent adaptation of the clustered regulatory interspaced short palindromic repeats (CRISPR)/CRISPR-associated protein 9 (Cas9) system for targeted genome engineering has led to its widespread application in many fields worldwide. In order to gain a better understanding of the design rules of CRISPR/Cas9 systems, several groups have carried out large library-based screens leading to some insight into sequence preferences among highly active target sites. To facilitate CRISPR/Cas9 design, these studies have spawned a plethora of guide RNA (gRNA) design tools with algorithms based solely on direct or indirect sequence features. Here, we demonstrate that the predictive power of these tools is poor, suggesting that sequence features alone cannot accurately inform the cutting efficiency of a particular CRISPR/Cas9 gRNA design. Furthermore, we demonstrate that DNA target site accessibility influences the activity of CRISPR/Cas9. With further optimization, we hypothesize that it will be possible to increase the predictive power of gRNA design tools by including both sequence and target site accessibility metrics. © 2017 The Authors. Experimental Physiology © 2017 The Physiological Society.

Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

Energy Technology Data Exchange (ETDEWEB)

Raja Shekhar, S. S.; Bhatawadekar, Shantanu; Krishna Murthy, Y. V.N., [Regional Remote Sensing Service Centre, Department of Space, Nagpur (India); Srinivas, C. V.; Venkatesan, [Radiological Safety Division, Radiological Safety and Environmental Group, Indira Gandhi Centre for Atomic Research, Kalapakkam (India)

2012-07-01

An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

International Nuclear Information System (INIS)

Raja Shekhar, S.S.; Bhatawadekar, Shantanu; Krishna Murthy, Y.V.N.; Srinivas, C.V.; Venkatesan

2012-01-01

An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings site at Ambrosia Lake, New Mexico

International Nuclear Information System (INIS)

Matthews, M.L.; Mitzelfelt, R.

1991-11-01

This Remedial Action Plan (RAP) has been developed to serve a dual purpose. It presents the series of activities that is proposed by the US Department of Energy (DOE) to stabilize and control radioactive materials at the inactive Phillips/United Nuclear uranium processing site designated as the Ambrosia Lake site in McKinley County, New Mexico. It also serves to document the concurrence of both State of New Mexico and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the state and concurrence by NRC, becomes Appendix B of the Cooperative Agreement

Site study plan for EDBH [Engineering Design Boreholes] No. 1 and 2: Revision 1

International Nuclear Information System (INIS)

1987-12-01

This site study plan describes the Engineering Design Boreholes 1 and 2 field activities to be conducted during early stages of Site Characterization at the Deaf Smith County site, Texas. The field program has been designed to provide data useful in addressing information/data needs resulting from federal/state/local regulations and repository program requirements. A borehole will be drilled at the centerline of each of the planned exploratory shaft locations. The subsurface rock and fluids will be sampled as the boreholes are advanced to total depth of about 2600 ft. Continuous rock core will be taken below the base of the Dockum Group. Hydrologic testing will occur in units thought to be water bearing and in units of particular interest for shaft seals. Field methods/tests are chosen that provide the best or only means of obtaining the required data. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. Drilling will not begin until after site ground-water baseline conditions have been established. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 28 refs., 10 figs., 4 tabs

Report of the Department of Energy (DOE) Office of Energy Research Review Committee on the site-specific conceptual design of the Superconducting Super Collider

International Nuclear Information System (INIS)

1990-09-01

After it was established in early 1989, the Superconducting Super Collider Laboratory (SSCL) began to prepare a detailed site-specific SSC conceptual design, including cost and schedule estimates. As detailed in the SSC Site-Specific Conceptual Design Report (SCDR), this design builds upon the design in the March 1986 SSC Conceptual Design Report (CDR) and takes into account characteristics of the SSC site, results of continuing magnet R ampersand D, and advances in accelerator design

Development of variable LRFD \\0x03C6 factors for deep foundation design due to site variability.

Science.gov (United States)

2012-04-01

The current design guidelines of Load and Resistance Factor Design (LRFD) specifies constant values : for deep foundation design, based on analytical method selected and degree of redundancy of the pier. : However, investigation of multiple sites in ...

Methods for assessing mine site rehabilitation design for erosion impact

International Nuclear Information System (INIS)

Evans, K. G.

2000-01-01

Erosion of rehabilitated mines may result in landform instability, which in turn may result in exposure of encapsulated contaminants, elevated sediment delivery at catchment outlets, and subsequent degradation of downstream water quality. Rehabilitation design can be assessed using erosion and hydrology models calibrated to mine site conditions. Incision rates in containment structures can be quantified using 3-dimensional landform evolution simulation techniques. Sediment delivery at catchment outlets for various landform amelioration techniques can be predicted using process-based and empirical erosion-prediction models and sediment delivery ratios. The predicted sediment delivery can be used to estimate an average annual stream sediment load that can, in turn, be used to assess water quality impacts. Application of these techniques is demonstrated through a case study applied to a proposed rehabilitation design option for the Energy Resources of Australia Ltd (ERA) Ranger Mine in the Northern Territory of Australia. Copyright (2000) CSIRO Australia

Response spectra by blind faults for design purpose of stiff structures on rock site

International Nuclear Information System (INIS)

Hiroyuki Mizutani; Kenichi Kato; Masayuki Takemura; Kazuhiko Yashiro; Kazuo Dan

2005-01-01

The goal of this paper is to propose the response spectra by blind faults for seismic design of nuclear power facilities. It is impossible to evaluate earthquake ground motions from blind faults, because the size and the location of blind fault cannot be identified even if the detailed geological surveys are conducted. From the viewpoint of seismic design, it is crucial to investigate the upper level of earthquake ground motions due to blind faults. In this paper, 41 earthquakes that occurred in the upper crust in Japan and California are selected and classified into the active and the blind fault types. On the basis of near-source strong motion records observed on rock sites, upper level of response spectra by blind faults is examined. The estimated upper level is as follows: the peak ground acceleration is 450 cm/s 2 , the flat level of the acceleration response spectra is 1200 cm/s 2 , and the flat level of the velocity response spectra is 100 cm/s on rock sites with shear wave velocity Vs of about 700 m/s. The upper level can envelop the observed response spectra in near-source region on rock sites. (authors)

Title I conceptual design for Pit 6 landfill closure at Lawrence Livermore National Laboratory Site 300

International Nuclear Information System (INIS)

MacDonnell, B.A.; Obenauf, K.S.

1996-08-01

The objective of this design project is to evaluate and prepare design and construction documents for a closure cover cap for the Pit 6 Landfill located at Lawrence Livermore National Laboratory Site 300. This submittal constitutes the Title I Design (Conceptual Design) for the closure cover of the Pit 6 Landfill. A Title I Design is generally 30 percent of the design effort. Title H Design takes the design to 100 percent complete. Comments and edits to this Title I Design will be addressed in the Title II design submittal. Contents of this report are as follows: project background; design issues and engineering approach; design drawings; calculation packages; construction specifications outline; and construction quality assurance plan outline

Design criteria for a worldwide directory of radioactively contaminated sites (DRCS)

International Nuclear Information System (INIS)

2001-11-01

The publication attempts to fulfil two main objectives: (a) to describe the activities and underlying considerations and concepts for the development by the IAEA of a worldwide Directory of Radioactively Contaminated Sites; (b) to give some recommendations for the development of such directories at the Member States level. In addition to a discussion of the conceptual considerations on the design of an IAEA-level directory, the results of previous efforts on data collation are presented. The DRCS also intends to collate technical information on remedial actions taken or proposed, thus giving examples for consultation in similar cases. Hence, the information available in such a Directory is intended to provide decision makers with a useful reference frame for their own actions. In this the IAEA attempts to assume the role of a clearing-house of information pertinent to characterization of radioactively contaminated sites and their remediation and restoration

Design criteria for a worldwide directory of radioactively contaminated sites (DRCS)

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-11-01

The publication attempts to fulfil two main objectives: (a) to describe the activities and underlying considerations and concepts for the development by the IAEA of a worldwide Directory of Radioactively Contaminated Sites; (b) to give some recommendations for the development of such directories at the Member States level. In addition to a discussion of the conceptual considerations on the design of an IAEA-level directory, the results of previous efforts on data collation are presented. The DRCS also intends to collate technical information on remedial actions taken or proposed, thus giving examples for consultation in similar cases. Hence, the information available in such a Directory is intended to provide decision makers with a useful reference frame for their own actions. In this the IAEA attempts to assume the role of a clearing-house of information pertinent to characterization of radioactively contaminated sites and their remediation and restoration.

Savannah River Site reactor hardware design modification study

International Nuclear Information System (INIS)

Fisher, J.E.

1990-01-01

A study was undertaken to assess the merits of proposed design modifications to the Savannah River Site (SRS) reactors. The evaluation was based on the responses calculated by the RELAP5 systems code to double-ended guillotine break loss-of-coolant-accidents (DEGB LOCAs). The three concepts evaluated were (a) elevated plenum inlet piping with a guard vessel and clamshell enclosures, (b) closure of both rotovalves in the affected loop, and (c) closure of the pump suction valve in the affected loop. Each concept included a fast reactor shutdown (to 65% power in 100 ms) and a 2-s ac pump trip. System recovery potential was evaluated for break locations at the pump suction, the pump discharge, and the plenum inlet. The code version used was RELAP5/MOD2.5 version 3d3, a preliminary version of RELAP5/MOD3. The model was a three-dimensional representation of the K-Reactor water plenum and moderator tank. It included explicit representations of all six loops, which were based on the configuration of L-Reactor. A combination of features is recommended to ensure liquid inventory recovery for all break locations. Valve closure design performance for a break location in the short section of piping between the reactor concrete shield and the pump suction valve would benefit from the clamshell enclosing that section of piping. 7 refs., 10 figs., 2 tabs

Siting Practices and Site Licensing Process for New Reactors in Canada

International Nuclear Information System (INIS)

Vos, Marcel de

2011-01-01

'Siting' in Canada is composed of Site Evaluation and Site Selection. As outlined in CNSC Regulatory Document RD-346 Site Evaluation for New Nuclear Power Plants (based on IAEA NS-R-3), prior to the triggering of the Environmental Assessment (EA) and licensing processes, the proponent is expected to use a robust process to characterize proposed sites over the full life cycle of the facility, and then develop a fully documented defense of the site selection case. This case forms the backbone for submissions in support of the EA and the application for a License to Prepare Site which will be reviewed by the CNSC and other applicable federal authorities. The Environmental Assessment process and License to Prepare Site in Canada do not require a proponent to select a specific design; however, CNSC does not accept a 'black box' approach to siting. CNSC balances the level of design information required with the extent of safety assurance desired for any designs being contemplated for the proposed site. Nevertheless, the design information submitted must be sufficient to justify the site as suitable for all future licensing stages. The depth of plant design information contributes significantly to the credibility of the applicant's case for both the EA and application for License to Prepare Site. The review process utilizes an assessment plan with defined review stages and timelines. The outcome of these reviews is a series of recommendations to a federal government appointed Joint Review Panel (which also serves as a panel of the 'Commission') which, following public hearings, renders a decision regarding the EA, and subsequently, the application for a License to Prepare Site. (author)

Site layout and balance of plant design for an accelerator-driven materials processing complex

Energy Technology Data Exchange (ETDEWEB)

Cunliffe, J.; Taussig, R.; Ghose, S. [Bechtel Corporation, San Francisco, CA (United States)] [and others

1995-10-01

High energy proton beam accelerators are under consideration for use in radioisotope production, surplus weapons material destruction, radioactive waste transmutation, and thorium-based energy conversion cycles. While there are unique aspects to each of these applications that must be accommodated in the design of the associated facility, all share a set of fundamental characteristics that in large measure dictate the site layout features and many balance-of-plant (BOP) design requirements found to be common to all. This paper defines these key design determinants and goes on to discuss the manner in which they have been accommodated in the pre-conceptual design for a particular materials production application. An estimate of the costs associated with this BOP design is also presented with the aim of guiding future evaluations where the basic plant designs are similar to that of this specific case.

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado: Remedial Action Selection Report. Preliminary final

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

This proposed remedial action plan incorporates the results of detailed investigation of geologic, geomorphic, and seismic conditions at the proposed disposal site. The proposed remedial action will consist of relocating the uranium mill tailings, contaminated vicinity property materials, demolition debris, and windblown/waterborne materials to a permanent repository at the proposed Burro Canyon disposal cell. The proposed disposal site will be geomorphically stable. Seismic design parameters were developed for the geotechnical analyses of the proposed cell. Cell stability was analyzed to ensure long-term performance of the disposal cell in meeting design standards, including slope stability, settlement, and liquefaction potential. The proposed cell cover and erosion protection features were also analyzed and designed to protect the RRM (residual radioactive materials) against surface water and wind erosion. The location of the proposed cell precludes the need for permanent drainage or interceptor ditches. Rock to be used on the cell top-, side-, and toeslopes was sized to withstand probable maximum precipitation events.

"Less Clicking, More Watching": Results from the User-Centered Design of a Multi-Institutional Web Site for Art and Culture.

Science.gov (United States)

Vergo, John; Karat, Clare-Marie; Karat, John; Pinhanez, Claudio; Arora, Renee; Cofino, Thomas; Riecken, Doug; Podlaseck, Mark

This paper summarizes a 10-month long research project conducted at the IBM T.J. Watson Research Center aimed at developing the design concept of a multi-institutional art and culture web site. The work followed a user-centered design (UCD) approach, where interaction with prototypes and feedback from potential users of the web site were sought…

On-site and off-site activities

International Nuclear Information System (INIS)

Martin, H.D.

1986-01-01

Design principles for NPP training programs. Effects of NPP contracts. Effects of domestic industrial activities. The role of international bodies. Requirements for on-site training. Training abroad, technical, financial and social aspects. Training center on-site, an evaluation. (orig.)

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Remedial action selection report

International Nuclear Information System (INIS)

1991-12-01

The uranium mill tailings site near Durango, Colorado, was one of 24 inactive uranium mill sites designated to be remediated by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's Remedial Action Plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which has been developed to serve a two-fold purpose. First, it describes the activities that have been conducted by the DOE to accomplish remediation and long-term stabilization and control of the radioactive materials at the inactive uranium mill processing site near Durango, Colorado. Secondly, this document and the rest of the RAP, upon concurrence and execution by the DOE, the State of Colorado, and the NRC, become Appendix B of the Cooperative Agreement between the DOE and the State of Colorado

Design of Buoys for Mounting Wind Turbines at Exposed Sites

Science.gov (United States)

Erdoğan, Beytullah; Çelıkkol, Barbaros; Swift, Robinson

2018-04-01

In this study, two designs for a buoy capable of supporting a 10 kW wind turbine and its tower were developed to operate at the University of New Hampshire's Center of Ocean Renewable Energy testing site located off the Isles of Shoals, New Hampshire. The buoys are to be moored by a catenary chain system. To evaluate wave response, two Froude-scaled models were constructed, tested, and compared at the Ocean Engineering wave tank at the University of New Hampshire. These buoys have been implemented and compared with wave tank measurements of the spar displacement at a reference elevation 2.44 m above the mean water level.

Bird Pollinator Visitation is Equivalent in Island and Plantation Planting Designs in Tropical Forest Restoration Sites

Directory of Open Access Journals (Sweden)

Ginger M. Thurston

2013-03-01

Full Text Available Active restoration is one strategy to reverse tropical forest loss. Given the dynamic nature of climates, human populations, and other ecosystem components, the past practice of using historical reference sites as restoration targets is unlikely to result in self-sustaining ecosystems. Restoring sustainable ecological processes like pollination is a more feasible goal. We investigated how flower cover, planting design, and landscape forest cover influenced bird pollinator visits to Inga edulis trees in young restoration sites in Costa Rica. I. edulis trees were located in island plantings, where seedlings had been planted in patches, or in plantation plantings, where seedlings were planted to cover the restoration area. Sites were located in landscapes with scant (10–21% or moderate (35–76% forest cover. Trees with greater flower cover received more visits from pollinating birds; neither planting design nor landscape forest cover influenced the number of pollinator visits. Resident hummingbirds and a migratory bird species were the most frequent bird pollinators. Pollination in the early years following planting may not be as affected by details of restoration design as other ecological processes like seed dispersal. Future work to assess the quality of various pollinator species will be important in assessing this idea.

Siting, design and construction of a deep geological repository for the disposal of high level and alpha bearing wastes

International Nuclear Information System (INIS)

1990-06-01

The main objective of this document is to summarize the basic principles and approaches to siting, design and construction of a deep geological repository for disposal of high level and alpha bearing radioactive wastes, as commonly agreed upon by Member States. This report is addressed to decision makers and technical managers as well as to specialists planning for siting, design and construction of geological repositories for disposal of high level and alpha bearing wastes. This document is intended to provide Member States of the IAEA with a summary outline for the responsible implementing organizations to use for siting, designing and constructing confinement systems for high level and alpha bearing radioactive waste in accordance with the protection objectives set by national regulating authorities or derived from safety fundamentals and standards of the IAEA. The protection objectives will be achieved by the isolation of the radionuclides from the environment by a repository system, which consists of a series of man made and natural safety barriers. Engineered barriers are used to enhance natural geological containment in a variety of ways. They must complement the natural barriers to provide adequate safety and necessary redundancy to the barrier system to ensure that safety standards are met. Because of the long timescales involved and the important role of the natural barrier formed by the host rock, the site selection process is a key activity in the repository design and development programme. The choice of the site, the investigation of its geological setting, the exploration of the regional hydrogeological setting and the primary underground excavations are all considered to be part of the siting process. 16 refs

Site-specific issues related to structural/seismic design of an underground independent spent fuel storage installation (ISFSI)

International Nuclear Information System (INIS)

Tripathi, B.P.

2005-01-01

Utilities owning and operating commercial nuclear power plants (NPP) in USA may choose to build an underground Independent Spent Fuel Storage Installation (ISFSI) to store the spent nuclear fuels. The regulatory requirements and other guidance are based on 10 CFR Part 72, Regulatory Guide RG 3.73, Standard Review Plans NUREG-1536 and NUREG-1567, and Interim staff Guidance (ISG) documents as applicable. Structures, Systems, and Components (SSCs) classified as important to safety are designed to withstand the effects of site-specific environmental conditions and natural phenomena such as earthquake, tornado, flood, etc. An underground ISFSI for storage of spent nuclear fuel, presents some unique analysis and design challenges. This paper will briefly address some of these challenges and discuss site-specific loads, including seismic for the ISFSI design. (authors)

Automatic web site authoring with SiteGuide

NARCIS (Netherlands)

de Boer, V.; Hollink, V.; van Someren, M.W.; Kłopotek, M.A.; Przepiórkowski, A.; Wierzchoń, S.T.; Trojanowski, K.

2009-01-01

An important step in the design process for a web site is to determine which information is to be included and how the information should be organized on the web site’s pages. In this paper we describe ’SiteGuide’, a tool that automatically produces an information architecture for a web site that a

ONWI [Office of Nuclear Waste Isolation] 30% design review findings report for Exploratory Shaft Facility, Deaf Smith site

International Nuclear Information System (INIS)

1987-01-01

This document describes a review of the standards for the design of the high-level radioactive waste facility at the Deaf Smith, Texas site. It includes public comments and the official responses to the designs produced to date

A sensitivity analysis of hazardous waste disposal site climatic and soil design parameters using HELP3

International Nuclear Information System (INIS)

Adelman, D.D.; Stansbury, J.

1997-01-01

The Resource Conservation and Recovery Act (RCRA) Subtitle C, Comprehensive Environmental Response, Compensation, And Liability Act (CERCLA), and subsequent amendments have formed a comprehensive framework to deal with hazardous wastes on the national level. Key to this waste management is guidance on design (e.g., cover and bottom leachate control systems) of hazardous waste landfills. The objective of this research was to investigate the sensitivity of leachate volume at hazardous waste disposal sites to climatic, soil cover, and vegetative cover (Leaf Area Index) conditions. The computer model HELP3 which has the capability to simulate double bottom liner systems as called for in hazardous waste disposal sites was used in the analysis. HELP3 was used to model 54 combinations of climatic conditions, disposal site soil surface curve numbers, and leaf area index values to investigate how sensitive disposal site leachate volume was to these three variables. Results showed that leachate volume from the bottom double liner system was not sensitive to these parameters. However, the cover liner system leachate volume was quite sensitive to climatic conditions and less sensitive to Leaf Area Index and curve number values. Since humid locations had considerably more cover liner system leachate volume than and locations, different design standards may be appropriate for humid conditions than for and conditions

Discussion about design basis flood of site of research reactors by river

International Nuclear Information System (INIS)

Rong Feng; Zhao Jianjun; Du Qiaomin; Zhang Lingyan

2006-01-01

This paper presents the well-defined standard in relation to design the basis flood of the sites of research reactors by river. It is based on the concept of some relational standards, analysis of hydrological calculation technology and methods, and analysis of accident dangerous degrees of research reactor, as well as in combination with the engineering practices. The flood preventing standard for research reactors with higher power should be the same with that of the nuclear power plants. (authors)

Multiagency radiation survey and site investigation manual (MARSSIM): Survey design

International Nuclear Information System (INIS)

Abelquist, E.W.; Berger, J.D.

1996-01-01

This paper describes the MultiAgency Radiation Survey and Site Investigation Manual (MARSSIM) strategy for designing a final status survey. The purpose of the final status survey is to demonstrate that release criteria established by the regulatory agency have been met. Survey design begins with identification of the contaminants and determination of whether the radionuclides of concern exist in background. The decommissioned site is segregated into Class 1, Class 2, and Class 3 areas, based on contamination potential, and each area is further divided into survey units. Appropriate reference areas for indoor and outdoor background measurements are selected. Survey instrumentation and techniques are selected in order to assure that the instrumentation is capable of detecting the contamination at the derived concentration guideline level (DCGL). Survey reference systems are established and the number of survey data points is determined-with the required number of data points distributed on a triangular grid Pattern. Two suitistical tests are used to evaluate data from final status surveys. For contaminants that are b, present in background, the Wilcoxon Rank Sum test is used; for contaminants that are not present in background, the Wilcoxon Signed Rank (or Sign) test is used. The number of data points needed to satisfy these nonparametric tests is based on the contaminant DCGL value, the expected Standard deviation of the contaminant in background and in the survey unit, and the acceptable probability of making Type I and Type II decision errors. The MARSSIM also requires a reasonable level of assurance that any small areas of elevated residual radioactivity that could be significant relative to regulatory limits are not missed during the final status survey. Measurements and sampling on a specified grid size are used to obtain an adequate assurance level that small locations of elevated radioactivity will Still satisfy DCGLs-applicable to small areas

Evaluation and design of drained low-level radioactive disposal sites. Final report

International Nuclear Information System (INIS)

Eichholz, G.G.

1984-12-01

Low-level disposal in shallow trenches has been the subject of much critical assessment in recent years. Historically most trenches have been located in fairly permeable settings and any liquid waste stored has migrated at rates limited mainly by hydraulic effects and the ion exchange capacity of underlying soil minerals. Attempts to minimize such seepage by choosing sites in very impermeable settings lead to overflow and surface runoff, whenever the trench cap is breached by subsidence or erosion. The work described in this report was directed to an optimum compromise situation where less reliance is placed on cap permanence, any ground seepage is directed and controlled, and the amount of waste leaching that would occur is minimized by keeping the soil surrounding the waste at only residual moisture levels at all times. Measurements have been conducted to determine these residual levels for some representative soils, to estimate the impact on waste migration of mainly unsaturated flow conditions, and to generate a conceptual design of a disposal facility which would provide adequate drainage to keep the waste from being exposed to continuous leaching by standing water. An attempt has also been made to quantify the reduced source terms under such periodic, unsaturated flow conditions, but those tests have not been conclusive to date. For low-permeability soils the waste should be placed about 1 ft. above the saturated layer formed by suction forces immediately above the gravel layer. Since most disposal sites, even in humid regions of the United States, are exposed only to intermittent rainfall and as most trench designs incorporate some gravel base for drainage, the results of this project have broader applications in assessing actual migration conditions in shallow trench disposal sites. Similar considerations may also apply to disposal of hazardous wastes

Identification and characterization of inhibitors of human apurinic/apyrimidinic endonuclease APE1.

Directory of Open Access Journals (Sweden)

Anton Simeonov

2009-06-01

Full Text Available APE1 is the major nuclease for excising abasic (AP sites and particular 3'-obstructive termini from DNA, and is an integral participant in the base excision repair (BER pathway. BER capacity plays a prominent role in dictating responsiveness to agents that generate oxidative or alkylation DNA damage, as well as certain chain-terminating nucleoside analogs and 5-fluorouracil. We describe within the development of a robust, 1536-well automated screening assay that employs a deoxyoligonucleotide substrate operating in the red-shifted fluorescence spectral region to identify APE1 endonuclease inhibitors. This AP site incision assay was used in a titration-based high-throughput screen of the Library of Pharmacologically Active Compounds (LOPAC(1280, a collection of well-characterized, drug-like molecules representing all major target classes. Prioritized hits were authenticated and characterized via two high-throughput screening assays -- a Thiazole Orange fluorophore-DNA displacement test and an E. coli endonuclease IV counterscreen -- and a conventional, gel-based radiotracer incision assay. The top, validated compounds, i.e. 6-hydroxy-DL-DOPA, Reactive Blue 2 and myricetin, were shown to inhibit AP site cleavage activity of whole cell protein extracts from HEK 293T and HeLa cell lines, and to enhance the cytotoxic and genotoxic potency of the alkylating agent methylmethane sulfonate. The studies herein report on the identification of novel, small molecule APE1-targeted bioactive inhibitor probes, which represent initial chemotypes towards the development of potential pharmaceuticals.

Evaluation of the Overall Costs for the Croatian Repository: Varying Site, Design and Financial Parameters

International Nuclear Information System (INIS)

Kucar-Dragicevic, S.; Subasic, D.; Lebegner, J.

2000-01-01

Preliminary preparations for the construction of a LILW repository in Croatia included a number of activities and projects related to the siting process, safety assessment, disposal technology and repository design, and public acceptance issues. Costs evaluations have always been a part of the developing project documentation. However, only the estimates of the facility construction and equipment acquisition costs had been included, while other costs associated with the project development and management have not been considered up to now. For the first time the infrastructure status at the potential sites has been evaluated, and the costs of the repository operations as well as the post-closure management has been estimated. Cost parameters have been considered from both technical and fiscal points of view, comparing their relative influence on the overall repository costs. Assessment of the total project costs in eight cases for the four preferential sites and two repository designs gave a clearer picture of the development and management costs differences for the considered options. Without considerations of the operational and post-operational repository management expenses, the total project costs appear to have been heavily underestimated. Also, while the construction costs for the tunnel and the surface type repositories are significantly different, this influence of the repository type on the total project costs becomes far less important when the later phases management expenses are added. Finally, the role of fiscal parameters may further diminish the site and technology impacts on the overall costs. (author)

The principles of design of a shallow disposal site for low and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Holmes, R.E.

1985-01-01

This paper addresses the principles of design of a shallow disposal site for low and intermediate level radioactive wastes. The objective of the author is to review the need for shallow land disposal facilities in the UK and to propose design principles which will protect the public and operatives from excessive risk. It is not the intent of the author to present a detailed design of facility which will meet the design standards proposed although such a design is feasible and within the scope of currently available technology. The principles and standards proposed in this paper are not necessarily those of PPC Consultant Services Ltd. or NEI Waste Technologies Ltd. (author)

Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

International Nuclear Information System (INIS)

Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

2011-01-01

The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

Energy Technology Data Exchange (ETDEWEB)

Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

2011-11-01

The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

Issues and recent advances in optimal experimental design for site investigation (Invited)

Science.gov (United States)

Nowak, W.

2013-12-01

This presentation provides an overview over issues and recent advances in model-based experimental design for site exploration. The addressed issues and advances are (1) how to provide an adequate envelope to prior uncertainty, (2) how to define the information needs in a task-oriented manner, (3) how to measure the expected impact of a data set that it not yet available but only planned to be collected, and (4) how to perform best the optimization of the data collection plan. Among other shortcomings of the state-of-the-art, it is identified that there is a lack of demonstrator studies where exploration schemes based on expert judgment are compared to exploration schemes obtained by optimal experimental design. Such studies will be necessary do address the often voiced concern that experimental design is an academic exercise with little improvement potential over the well- trained gut feeling of field experts. When addressing this concern, a specific focus has to be given to uncertainty in model structure, parameterizations and parameter values, and to related surprises that data often bring about in field studies, but never in synthetic-data based studies. The background of this concern is that, initially, conceptual uncertainty may be so large that surprises are the rule rather than the exception. In such situations, field experts have a large body of experience in handling the surprises, and expert judgment may be good enough compared to meticulous optimization based on a model that is about to be falsified by the incoming data. In order to meet surprises accordingly and adapt to them, there needs to be a sufficient representation of conceptual uncertainty within the models used. Also, it is useless to optimize an entire design under this initial range of uncertainty. Thus, the goal setting of the optimization should include the objective to reduce conceptual uncertainty. A possible way out is to upgrade experimental design theory towards real-time interaction

Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

International Nuclear Information System (INIS)

Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

1986-01-01

This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs

Hard rock excavation at the CSM/OCRD test site using Swedish blast design techniques

International Nuclear Information System (INIS)

Holmberg, R.

1983-09-01

This report is the third in a series describing research conducted by the Colorado School of Mines for the Office of Crystalline Repository Development (OCRD) to determine the extent of blast damage in rock surrounding an underground opening. A special room, called the CSM/OCRD room, was excavated at the CSM experimental mine for the purpose of assessing blast damage in the rock around the room. Even though this mine is not proposed as a nuclear waste repository site, the instrumentation and methods of blast damage assessment developed in this project are applicable to proposed repository sites. This report describes the application of Swedish blasting technology for the excavation of the test room. The design of the blasting patterns including the selection of explosives, hole sizes and location, explosive loading densities, and delay intervals is based upon the theories of Langefors and Kihlstrom in combination with methods used at the Swedish Detonic Research Foundation for minimizing unwanted rock damage. The practical application of the design procedures to seven rounds and the achieved results is discussed

Site study plan for Exploratory shaft facilities design foundation boreholes (shaft surface facility foundation borings), Deaf Smith County Site, Texas: Surface-based geotechnical field program: Preliminary draft

International Nuclear Information System (INIS)

1987-12-01

This site study plan describes the Exploratory Shaft Facilities (ESF) Design Foundation Boreholes field activities to be conducted during early stages of Site Characterization at the Deaf Smith County, Texas, site. The field program has been designed to provide data useful in addressing information/data needs resulting from federal/state/local regulations, and repository program requirements. Approximately 50 foundation boreholes will be drilled within the ESP location to provide data necessary for design of the ESF and to satisfy applicable shaft permitting requirements. Soils and subsurface rock will be sampled as the foundation boreholes are advanced. Soil samples or rock core will be taken through the Blackwater Draw and Ogallala Formations and the Dockum Group. Hydrologic testing will be performed in boreholes that penetrates the water table. In-situ elastic properties will be determined from both the soil strata and rock units along the length of the boreholes. Field methods/tests are chosen that provide the best or only means of obtaining the required data. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. Drilling will not begin until after site ground water baseline conditions have been established. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 25 refs., 10 figs., 6 tabs

Conceptual design report, TWRS Privatization Phase I, site development and roads, subproject W-505

International Nuclear Information System (INIS)

Singh, G.

1997-01-01

This document includes Conceptual Design Report (CDR) for the site development, construction of new roads and improvements at existing road intersections, habitat mitigation, roadway lighting, and construction power needed for the construction of two Private Contractor (PC) Facilities. Approximately 50 hectare (124 acres) land parcel, east of the Grout Facility, is planned for the PC facilities

Technology development for the design of shallow land burial facilities at arid sites

International Nuclear Information System (INIS)

Nyhan, J.W.; Abeele, W.V.; Cokal, E.J.; Perkins, B.A.; Lane, L.J.

1984-01-01

The field research program involving technology development for arid shallow land burial (SLB) sites is described. Field tests of biointrusion barriers at waste disposal sites and in experimental plots at Los Alamos are reported. Results of completed and on-going experiments with migration barriers for water and contaminant movement are presented. An envelope wick experiment for subsurface water management is described, and preliminary field data are reported. An integrated field experiment was designed to test individual SLB component tests related to erosion control, biobarriers, and subsurface capillary and migration barriers, and the progress made in emplacing the experiment is presented. Efforts to utilize the field data collected to validate hydrologic models (TRACR3D) important to waste management strategies are also presented. 11 references, 14 figures, 1 table

New Reactor Siting in Finland, Hanhikivi Site in Pyhaejoki - STUK preliminary safety assessment

International Nuclear Information System (INIS)

Nevalainen, Janne

2013-01-01

STUK has performed a preliminary assessment of the Decision-in-Principle on the Fennovoima application. A variety of factors must be considered in the selection of a site, including effects of the site on the plant design and the effects of the plant on the site environment. These include external hazards, both natural and human-induced. Since this is a new site, an extensive siting process is followed, that can include an EIA. A site survey is performed to identify candidate sites, after investigating a large region and rejecting unsuitable sites. The remaining sites are then screened and compared on the basis of safety and other considerations to select one or more preferred sites. Natural hazards include geology, seismology, hydrology and meteorology. Offshore ice will be a particular hazard for this plant, since the site is on average only 1.5 m above sea level. The design basis earthquake corresponds to a return frequency of 100,000 years, with 50 % confidence. The existing sites in southern Finland used a design peak ground acceleration of 0.1 g with the ground response spectrum maximum at 10 Hz. The candidate sites in northern Finland will require a peak ground acceleration of 0.2 g with the ground response spectrum maximum at 25 Hz

Design Optimization and Site Matching of Direct-Drive Permanent Magnet Wind Generator Systems

DEFF Research Database (Denmark)

Li, H.; Chen, Zhe

2009-01-01

This paper investigates the possible site matching of the direct-drive wind turbine concepts based on the electromagnetic design optimization of permanent magnet (PM) generator systems. Firstly, the analytical models of a three-phase radial-flux PM generator with a back-to-back power converter...... of the maximum wind energy capture, the rotor diameter and the rated wind speed of a direct-drive wind turbine with the optimum PM generator are determined. The annual energy output (AEO) is also presented using the Weibull density function. Finally, the maximum AEO per cost (AEOPC) of the optimized wind...... are presented. The optimum design models of direct-drive PM wind generation system are developed with an improved genetic algorithm, and a 500-kW direct-drive PM generator for the minimal generator active material cost is compared to demonstrate the effectiveness of the design optimization. Forty-five PM...

75 FR 38129 - Freescale Semiconductor, Inc., Hardware/Software Design and Manufacturing A Including On-Site...

Science.gov (United States)

2010-07-01

... Manufacturing A, Austin, Texas. The notice was published in the Federal Register on May 28, 2010 (75 FR 30070...Logic, Inc., Austin, TX; Amended Certification Regarding Eligibility To Apply for Worker Adjustment..., Design Solutions, Inc., Veriseo, SilconElite and MicroLogic, Inc. were employed on-site at the Austin...

Design of a permanent Cd-shielded epithermal neutron irradiation site in the Syrian Miniature Neutron Source Reactor

International Nuclear Information System (INIS)

Khattab, K.; Haddad, Kh.; Haj-Hassan, H.

2008-01-01

A Cd-shield (cylindrical shell 1 mm in thickness, 34 mm in diameter and 180 mm in length) was used to design a permanent epithermal neutron irradiation site for epithermal neutron activation analysis (ENAA) in the Syrian Miniature Neutron Source Reactor (MNSR). This site was achieved by shielding the surface of the aluminum tube of one of the outer irradiation sites. The calculated depression ratio of thermal neutron flux was 1/10. Homogeneity of the neutron flux in the first outer irradiation site has been found numerically using the WIMSD4 and CITATION codes and experimentally by irradiating five short copper wires using the outer irradiation capsule. Good agreement was obtained between the calculated and the measured results of the neutron flux distributions. (author)

Design of a permanent Cd-shielded epithermal neutron irradiation site in the Syrian Miniature Neutron Source Reactor

International Nuclear Information System (INIS)

Khattab, K.; Haddad, Kh.; Haj-Hassan, H.

2009-01-01

A Cd-shield (cylindrical shell 1 mm in thickness, 34 mm in diameter and 180 mm in length) was used to design a permanent epithermal neutron irradiation site for epithermal neutron activation analysis (ENAA) in the Syrian Miniature Neutron Source Reactor (MNSR). This site was achieved by shielding the surface of the aluminum tube of one of the outer irradiation sites. The calculated depression ratio of thermal neutron flux was 1/10. Homogeneity of the neutron flux in the first outer irradiation site has been found numerically using the WIMSD4 and CITATION codes and experimentally by irradiating five short copper wires using the outer irradiation capsule. Good agreement was obtained between the calculated and the measured results of the neutron flux distributions. (author)

Hanford Site peak gust wind speeds

International Nuclear Information System (INIS)

Ramsdell, J.V.

1998-01-01

Peak gust wind data collected at the Hanford Site since 1945 are analyzed to estimate maximum wind speeds for use in structural design. The results are compared with design wind speeds proposed for the Hanford Site. These comparisons indicate that design wind speeds contained in a January 1998 advisory changing DOE-STD-1020-94 are excessive for the Hanford Site and that the design wind speeds in effect prior to the changes are still appropriate for the Hanford Site

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado. Final report

International Nuclear Information System (INIS)

1996-08-01

This document contains the page changes for Attachment 3, Ground Water Hydrology Report dated August, 1996 for the Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings at Slick Rock, Colorado. This portion of Attachment 3 contains the Table of Contents pages i and ii, and pages numbered 3-3 through 3-56 of the Ground Water Hydrology Report. Also included are the cover sheets for Appendix A, B, and C to Attachment 3

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho: Remedial action selection report for the Lowman UMTRA project site, Idaho

International Nuclear Information System (INIS)

Matthews, M.L.; Nagel, J.

1991-09-01

The inactive uranium mill tailings site near Lowman, Idaho, was designated as one of 24 abandoned uranium tailings sites to be remediated by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan and certify that the remedial action complies with the standards promulgated by the US Environmental Protection Agency (EPA). The remedial action plan (RAP), which includes this remedial action selection report (RAS), has been developed to serve a two-fold purpose. First, it describes the activities that are proposed by the DOE to accomplish long-term stabilization and control of residual radioactive materials at the inactive uranium processing site near Lowman, Idaho. Second, this document and the remainder of the RAP, upon concurrence and execution by the DOE, the State of Idaho, and the NRC, becomes Appendix B of the Cooperative Agreement (No. DE-FC04-85AL20535) between the DOE and the State of Idaho

SR 97 - Waste, repository design and sites. Background report to SR 97 SKB

International Nuclear Information System (INIS)

1999-10-01

SR 97 is a comprehensive analysis of long-term safety of a deep repository for spent nuclear fuel. The repository is assumed to be designed according to the KBS-3 method. Assessments are performed in SR 97 for three fictitious sites: Aberg, Beberg and Ceberg. One premise is that data used for assessment of the fictitious sites are to be taken from sites that have previously been investigated. The spent nuclear fuel is enclosed in copper canisters with an insert of cast iron. The canisters are emplaced in bored holes in the floor of the deposition tunnels. Around each canister, bentonite blocks are stacked which, after absorbing water and swelling, will isolate the canister from groundwater, hold the canister in place and retard transport of radionuclides from the canister to the surrounding rock. The spent nuclear fuel will emit heat for a long time, due to the decay heat. The maximum permissible temperature on the canister surface has been chosen at 100 deg C. The spacing between the deposition holes and between the deposition tunnels is adjusted site-specifically to meet this requirement. The thermal properties of the rock and the buffer material are of importance for how closely the deposition holes and tunnels can be spaced. After deposition, the deposition tunnels are backfilled with a mixture of bentonite and crushed rock. SR 97 examines above all the consequences of various scenarios and the handling of various types of uncertainties. The different repository sites illustrate normal properties for Swedish bedrock which are of importance for safety. To facilitate the work, the repositories on the three sites are configured as similarly as possible, which means for example that they are located at roughly the same depth and are fitted into the bedrock in a relatively similar fashion. Apart from the siting of a repository for spent nuclear fuel, the site may need to house a separate repository for other long-lived waste. This possibility has been considered in

SR 97 - Waste, repository design and sites. Background report to SR 97 SKB

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-10-01

SR 97 is a comprehensive analysis of long-term safety of a deep repository for spent nuclear fuel. The repository is assumed to be designed according to the KBS-3 method. Assessments are performed in SR 97 for three fictitious sites: Aberg, Beberg and Ceberg. One premise is that data used for assessment of the fictitious sites are to be taken from sites that have previously been investigated. The spent nuclear fuel is enclosed in copper canisters with an insert of cast iron. The canisters are emplaced in bored holes in the floor of the deposition tunnels. Around each canister, bentonite blocks are stacked which, after absorbing water and swelling, will isolate the canister from groundwater, hold the canister in place and retard transport of radionuclides from the canister to the surrounding rock. The spent nuclear fuel will emit heat fora long time, due to the decay heat. The maximum permissible temperature on the canister surface has been chosen at 100 deg C. The spacing between the deposition holes and between the deposition tunnels is adjusted site-specifically to meet this requirement. The thermal properties of the rock and the buffer material are of importance for how closely the deposition holes and tunnels can be spaced. After deposition, the deposition tunnels are backfilled with a mixture of bentonite and crushed rock. SR 97 examines above all the consequences of various scenarios and the handling of various types of uncertainties. The different repository sites illustrate normal properties for Swedish bedrock which are of importance for safety. To facilitate the work, the repositories on the three sites are configured as similarly as possible, which means for example that they are located at roughly the same depth and are fitted into the bedrock in a relatively similar fashion. Apart from the siting of a repository for spent nuclear fuel, the site may need to house a separate repository for other long-lived waste. This possibility has been considered in

SiteGuide: An example-based approach to web site development assistance

NARCIS (Netherlands)

Hollink, V.; de Boer, V.; van Someren, M.; Filipe, J.; Cordeiro, J.

2009-01-01

We present ‘SiteGuide’, a tool that helps web designers to decide which information will be included in a new web site and how the information will be organized. SiteGuide takes as input URLs of web sites from the same domain as the site the user wants to create. It automatically searches the pages

Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices

Energy Technology Data Exchange (ETDEWEB)

1993-03-18

This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

Site Identification by Ligand Competitive Saturation (SILCS) Simulations for Fragment-Based Drug Design

OpenAIRE

Faller, Christina E.; Raman, E. Prabhu; MacKerell, Alexander D.; Guvench, Olgun

2015-01-01

Fragment-based drug design (FBDD) involves screening low molecular weight molecules (“fragments”) that correspond to functional groups found in larger drug-like molecules to determine their binding to target proteins or nucleic acids. Based on the principle of thermodynamic additivity, two fragments that bind non-overlapping nearby sites on the target can be combined to yield a new molecule whose binding free energy is the sum of those of the fragments. Experimental FBDD approaches, like NMR ...

Convective boiling in a parallel microchannel heat sink with a diverging cross-section design and artificial nucleation sites

International Nuclear Information System (INIS)

Lu, Chun Ting; Pan, Chin

2009-01-01

To develop a highly stable boiling heat transfer microchannel heat sink, the three types of diverging microchannels, namely Type-1, Type-2 and Type-3, were designed to explore experimentally the effect of different distribution of artificial nucleation sites on enhancing boiling heat transfer in 10 parallel diverging microchannels with a mean hydraulic diameter of 120 μm. The Type-1 system is with no cavities, Type-2 is with cavities distributed uniformly along the downstream half of the channel, while Type-3 is with cavities distributed uniformly along the whole channel. The artificial nucleation sites are laser-etched pits on the channel bottom wall with a mouth diameter of about 20-22 μm based on the heterogeneous nucleation theory. The results of the present study reveal the presence of the artificial nucleation sites for flow boiling in parallel diverging microchannel significantly reduces the wall superheat and enhances the boiling heat transfer performance. Additionally, the Type-3 design demonstrates the best boiling heat transfer performance. (author)

Development of technology for the design of shallow land burial facilities at arid sites

International Nuclear Information System (INIS)

Nyhan, J.W.; Abeele, W.V.; Drennon, B.J.; Herrera, W.J.; Lopez, E.A.; Langhorst, G.J.; Stallings, E.A.; Walker, R.D.; Martinez, J.L.

1985-01-01

The Los Alamos field research program involving technology development for arid shallow land burial (SLB) sites is described. Field data are presented for an integrated field experiment, which was designed to test individual SLB component experiments related to erosion control, biobarriers, and subsurface capillary and migration barriers. Field tests of biointrusion barriers at waste disposal sites and in experimental plots are reported. The results of a joint DOE/NRC experiment to evaluate leaching and transport of sorbing (Cs, Sr, Li) and nonsorbing (I, Br) solutes in sandy silt backfill are presented for steady-state and unsteady-state flow conditions. A capillary barrier experiment performed in a large caisson (3-m diameter, 6.1 m deep) is described and a year's worth of field data is presented

Sampling design and procedures for fixed surface-water sites in the Georgia-Florida coastal plain study unit, 1993

Science.gov (United States)

Hatzell, H.H.; Oaksford, E.T.; Asbury, C.E.

1995-01-01

The implementation of design guidelines for the National Water-Quality Assessment (NAWQA) Program has resulted in the development of new sampling procedures and the modification of existing procedures commonly used in the Water Resources Division of the U.S. Geological Survey. The Georgia-Florida Coastal Plain (GAFL) study unit began the intensive data collection phase of the program in October 1992. This report documents the implementation of the NAWQA guidelines by describing the sampling design and procedures for collecting surface-water samples in the GAFL study unit in 1993. This documentation is provided for agencies that use water-quality data and for future study units that will be entering the intensive phase of data collection. The sampling design is intended to account for large- and small-scale spatial variations, and temporal variations in water quality for the study area. Nine fixed sites were selected in drainage basins of different sizes and different land-use characteristics located in different land-resource provinces. Each of the nine fixed sites was sampled regularly for a combination of six constituent groups composed of physical and chemical constituents: field measurements, major ions and metals, nutrients, organic carbon, pesticides, and suspended sediments. Some sites were also sampled during high-flow conditions and storm events. Discussion of the sampling procedure is divided into three phases: sample collection, sample splitting, and sample processing. A cone splitter was used to split water samples for the analysis of the sampling constituent groups except organic carbon from approximately nine liters of stream water collected at four fixed sites that were sampled intensively. An example of the sample splitting schemes designed to provide the sample volumes required for each sample constituent group is described in detail. Information about onsite sample processing has been organized into a flowchart that describes a pathway for each of

Site development

International Nuclear Information System (INIS)

Gaynor, R.K.

1989-01-01

Development of a low-level radioactive waste land disposal facility is little different than any industrial development of similar scope. Consideration must be made for normal business and operations management, security, facility maintenance, traffic control and necessary amenities for personnel. The item specific to the low-level waste site is the handling of radioactive waste materials and the regulatory and environmental protection procedures that must be planned for and accomodated in the site design and development. Each of these elements and the facility as a whole must be designed to be compatible with local land use plans, available transportation and support services, and the social and economic goals of the local community. Plans should also be made for quality control and orderly construction. This chapter deals with those aspects of the facility, its design and construction which are integral parts to the overall performance of the site

2009 Melbourne metropolitan sewerage strategy: a portfolio of decentralised and on-site concept designs.

Science.gov (United States)

Brown, V; Jackson, D W; Khalifé, M

2010-01-01

The bulk and retail water companies of the greater Melbourne area are developing the 2009 Metropolitan Sewerage Strategy to provide sustainable sewerage services to 2060. The objective of the strategy is to establish long term principles and near term actions to produce a robust sewage management system for Melbourne. Melbourne's existing sewerage system is largely centralised and discharges to two major treatment plants. Several small satellite treatment plants service local urban areas generally more distant from the centralised system. Decentralised and on-site wastewater systems are options for future sewage management and could play a role in local recycling. A portfolio of 18 on-site and decentralised concept designs was developed, applicable to the full range of urban development types in Melbourne. The concepts can be used in evaluation of metropolitan system configurations as part of future integrated water cycle planning. The options included secondary and tertiary treatment systems incorporating re-use of water for non potable uses, urine separation, black and greywater separation and composting toilets. On-site and cluster treatment systems were analysed. Each option is described by its indicative capital and operating costs, energy use and water and nutrient balances. This paper summarises and compares the portfolio mix of decentralized and on-site options in Melbourne's context.

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado: Final report

International Nuclear Information System (INIS)

1990-02-01

This radiologic characterization of tho two inactive uranium millsites at Rifle, Colorado, was conducted by Bendix Field Engineering Corporation (Bendix) for the US Department of Energy (DOE), Grand Junction Projects Office, in accord with a Statement of Work prepared by the DOE Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor, Jacobs Engineering Group, Inc. (Jacobs). The purpose of this project is to define the extent of radioactive contamination at the Rifle sites that exceeds US Environmental Protection Agency, (EPA) standards for UMTRA sites. The data presented in this report are required for characterization of the areas adjacent to the tailings piles and for the subsequent design of cleanup activities. An orientation visit to the study area was conducted on 31 July--1 August 1984, in conjunction with Jacobs, to determine the approximate extent of contaminated area surrounding tho piles. During that visit, survey control points were located and baselines were defined from which survey grids would later be established; drilling requirements were assessed; and radiologic and geochemical data were collected for use in planning the radiologic fieldwork. The information gained from this visit was used by Jacobs, with cooperation by Bendix, to determine the scope of work required for the radiologic characterization of the Rifle sites. Fieldwork at Rifle was conducted from 1 October through 16 November 1984

Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

International Nuclear Information System (INIS)

1993-01-01

This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz. This document, Volume IV, provides Appendix 8.B, Laboratory Investigations of Dynamic Properties of Reference Sites

Preliminary thermal/thermomechanical analyses of the Site Characterization Plan's Conceptual Design for a repository containing horizontally emplaced waste packages at the Deaf Smith County site

International Nuclear Information System (INIS)

Ghantous, N.Y.; Raines, G.E.

1987-10-01

This report presents thermal/thermomechanical analyses of the Site Characterization Plan Conceptual Design for horizontal package emplacement at the Deaf Smith County site, Texas. The repository was divided into three geometric regions. Then two-dimensional finite-element models were set up to approximate the three-dimensional nature of each region. Thermal and quasistatic thermomechanical finite-element analyses were performed to evaluate the thermal/thermomechanical responses of the three regions. The exponential-time creep law was used to represent the creep behavior of salt rock. The repository design was evaluated by comparing the thermal/thermomechanical responses obtained for the three regions with interim performance constraints. The preliminary results show that all the performance constraints are met except for those of the waste package. The following factors were considered in interpreting these results: (1) the qualitative description of the analytical responses; (2) the limitations of the analyses; and (3) either the conclusions based on overall evaluation of limitations and analytical results or the conclusions based on the fact that the repository design may be evaluated only after further analyses. Furthermore, a parametric analysis was performed to estimate the effect of material parameters on the predicted thermal/thermomechanical response. 23 refs., 34 figs., 9 tabs

Umatilla Satellite and Release Sites Project : Final Siting Report.

Energy Technology Data Exchange (ETDEWEB)

Montgomery, James M.

1992-04-01

This report presents the results of site analysis for the Umatilla Satellite and Release Sites Project. The purpose of this project is to provide engineering services for the siting and conceptual design of satellite and release facilities for the Umatilla Basin hatchery program. The Umatilla Basin hatchery program consists of artificial production facilities for salmon and steelhead to enhance production in the Umatilla River as defined in the Umatilla master plan approved in 1989 by the Northwest Power Planning Council. Facilities identified in the master plan include adult salmon broodstock holding and spawning facilities, facilities for recovery, acclimation, and/or extended rearing of salmon juveniles, and development of river sites for release of hatchery salmon and steelhead. The historic and current distribution of fall chinook, summer chinook, and coho salmon and steelhead trout was summarized for the Umatilla River basin. Current and future production and release objectives were reviewed. Twenty seven sites were evaluated for the potential and development of facilities. Engineering and environmental attributes of the sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

Discovery of novel STAT3 small molecule inhibitors via in silico site-directed fragment-based drug design.

Science.gov (United States)

Yu, Wenying; Xiao, Hui; Lin, Jiayuh; Li, Chenglong

2013-06-13

Constitutive activation of signal transducer and activator of transcription 3 (STAT3) has been validated as an attractive therapeutic target for cancer therapy. To stop both STAT3 activation and dimerization, a viable strategy is to design inhibitors blocking its SH2 domain phosphotyrosine binding site that is responsible for both actions. A new fragment-based drug design (FBDD) strategy, in silico site-directed FBDD, was applied in this study. A designed novel compound, 5,8-dioxo-6-(pyridin-3-ylamino)-5,8-dihydronaphthalene-1-sulfonamide (LY5), was confirmed to bind to STAT3 SH2 by fluorescence polarization assay. In addition, four out of the five chosen compounds have IC50 values lower than 5 μM for the U2OS cancer cells. 8 (LY5) has an IC50 range in 0.5-1.4 μM in various cancer cell lines. 8 also suppresses tumor growth in an in vivo mouse model. This study has demonstrated the utility of this approach and could be used to other drug targets in general.

Designing chemical soil characterization programs for mixed waste sites

International Nuclear Information System (INIS)

Meyers, K.A. Jr.

1989-01-01

The Weldon Spring Site Remedial Action Project is a remedial action effort funded by the U.S. Department of Energy. The Weldon Spring Site, a former uranium processing facility, is located in east-central Missouri on a portion of a former ordnance works facility which produced trinitrotoluene during World War II. As a result of both uranium and ordnance production, the soils have become both radiologically and chemically contaminated. As a part of site characterization efforts in support of the environmental documentation process, a chemical soil characterization program was developed. This program consisted of biased and unbiased sampling program which maximized areal coverage, provided a statistically sound data base and maintained cost effectiveness. This paper discusses how the general rationale and processes used at the Weldon Spring Site can be applied to other mixed and hazardous waste sites

Capturing Snapshots of APE1 Processing DNA Damage

Science.gov (United States)

Freudenthal, Bret D.; Beard, William A.; Cuneo, Matthew J.; Dyrkheeva, Nadezhda S.; Wilson, Samuel H.

2015-01-01

DNA apurinic-apyrimidinic (AP) sites are prevalent non-coding threats to genomic stability and are processed by AP endonuclease 1 (APE1). APE1 incises the AP-site phosphodiester backbone, generating a DNA repair intermediate that is potentially cytotoxic. The molecular events of the incision reaction remain elusive due in part to limited structural information. We report multiple high-resolution human APE1:DNA structures that divulge novel features of the APE1 reaction, including the metal binding site, nucleophile, and arginine clamps that mediate product release. We also report APE1:DNA structures with a T:G mismatch 5′ to the AP-site, representing a clustered lesion occurring in methylated CpG dinucleotides. These reveal that APE1 molds the T:G mismatch into a unique Watson-Crick like geometry that distorts the active site reducing incision. These snapshots provide mechanistic clarity for APE1, while affording a rational framework to manipulate biological responses to DNA damage. PMID:26458045

Site characterization plan:

International Nuclear Information System (INIS)

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

Design and operation of a low-level solid-waste disposal site at Los Alamos

International Nuclear Information System (INIS)

Balo, K.A.; Wilson, N.E.; Warren, J.L.

1982-01-01

Since the mid-1940's, approximately 185000 m 3 of low-level and transuranic radioactive solid waste, generated in operations at the Los Alamos National Laboratory, have been disposed of by on-site shallow land burial. Procedures and facilities have been designed and evaluated in the areas of waste acceptance, treatment and storage, disposal, traffic control, and support systems. The methodologies assuring the proper management and disposal of radioactive solid waste are summarized

Ocean Disposal Site Monitoring

Science.gov (United States)

EPA is responsible for managing all designated ocean disposal sites. Surveys are conducted to identify appropriate locations for ocean disposal sites and to monitor the impacts of regulated dumping at the disposal sites.

Design and performance of the Savannah River Site Billet Active Well Coincidence Counter

International Nuclear Information System (INIS)

Griffin, J.C.; Sadowski, E.T.

1991-01-01

The Savannah River Site (SRS) has acquired, installed, and tested a custom-built Billet Active Well (neutron) Coincidence Counter (BAWCC). The BAWCC is used to make accountability measurements of the 235 U content of U-Al coextrusion billets in the SRS fuel fabrication facility. The instrument design incorporates a unique center-source configuration, with two moderated americium-lithium (AmLi) neutron sources located in a central spindle that inserts through the center hole of the U-Al billets. This configuration, a result of earlier experimental studies at SRS, yields improved response and precision for billet assay when compared to the standard AWCC source arrangement. Initial tests of the BAWCC at SRS have yielded one-sigma uncertainties of 0.8--1.0% for a fifteen-minute assay. This paper will describe the design, testing program and performance characteristics of the BAWCC

Long-term cover design for low-level radioactive and hazardous waste sites as applied to the Rocky Flats Environmental Technology Site solar evaporation ponds

International Nuclear Information System (INIS)

Stenseng, S.E.; Nixon, P.A.

1996-01-01

The US Department of Energy (DOE) operated five lined solar evaporation ponds (SEPs) at the Rocky Flats Environmental Technology Site (RFETS) in Jefferson County, Colorado from 1953 until 1986. The SEPs were used primarily to store and evaporate low-level radioactive and hazardous process wastes. Operation of the SEPs has resulted in contamination of the surrounding soils, and may also provide a source of groundwater contamination. The DOE proposes to close the SEPs by consolidating the contaminated material beneath an engineered cover. The primary objective of the closure of such hazardous and radioactive sites is to limit the exposure of the general public to the contaminants for time periods ranging from 100 to 10,000 years. The goal of the SEPs engineered cover is to isolate hazardous and low-level radioactive soils for a minimum of 1,000 years. Since there is currently no existing regulatory design guidance for a 1,000-year engineered cover, the proposed design of the SEPs engineered cover is based on research and testing that has been conducted for many years at various DOE facilities in the US. This paper discusses the main design theories of the proposed engineered cover for the closure of the SEPs, and how the research and test results of these other programs have been used to arrive at the final cover configuration, the material selections, the component layering, layer thicknesses, and the balance and interaction between components to establish an overall effective cover system

Regulatory principles, criteria and guidelines for site selection, design, construction and operation of uranium tailings retention systems

International Nuclear Information System (INIS)

Coady, J.R.; Henry, L.C.

1978-01-01

Principles, criteria and guidelines developed by the Atomic Energy Control Board for the management of uranium mill tailings are discussed. The application of these concepts is considered in relation to site selection, design and construction, operation and decommissioning of tailings retention facilities

Advances and Challenges in the Implementation of DiD in Siting, Design, and Construction of Nuclear Installations in Vietnam

Energy Technology Data Exchange (ETDEWEB)

Nguyen, H.A., E-mail: nhanh@varans.vn [Vietnam Agency for Radiation and Nuclear Safety, Hanoi (Viet Nam)

2014-10-15

Vietnam is embarking on a development of a nuclear power program. The main focus is now on the initial 1000 MWe x 2 units of the nuclear power plant in Ninh Thuan province. Now, the nuclear projects of Vietnam are in the phase of siting approval and investment projects approval. The design assessment will be performed in 2013-2014; the construction and installation will be performed from now until the operating licensing is obtained in 2020-2021. With state of development of a nuclear power program in Vietnam, this paper only focuses on advances and challenges in the implementation of Defence in Depth (DID) in siting, design, and construction of nuclear installations in Vietnam. (author)

Design of NPP of new generation being constructed at Novovoronezh NPP site

International Nuclear Information System (INIS)

Afrov, A.; Berkovich, V.; Generalov, V.; Dragunov, Yu.; Krushelnitskij, V.

2000-01-01

The design of a new-generation nuclear power plant with advanced WWER-1000 units, currently under construction at Novovoronezh, is dealt with in considerable detail. Information is given on the general layout of the power plant, and the monoblock comprising the four-loop reactor plant with double containment, the turbine hall with two turbine-driven feedwater pumps and safety and auxiliary systems is described. In a separate building at the power plant site, a new fuel storage facility is located designed for extreme external effects. The operations involved in fuel handling, in both the storage facility and the reactor department, are mentioned. The management of various types of radioactive waste is highlighted. The basic principles of the engineering solutions pertaining to the plant's electrical part are outlined. The concept of the instrumentation and control system is explained. Information is also given on the double containment system. A considerable part of the presentation is devoted to the philosophy and concept of the power plant safety, to the results of safety evaluation and to the research carried out in this respect. The paper is concluded with a discussion of the experiments and analyses performed with the aim to justify the design solutions as regards the passive heat removal system. (A.K.)

Socioeconomic Site Study Plan: Draft

International Nuclear Information System (INIS)

1987-07-01

Social and economic issues and concerns of the Deak Smith County site area will be evaluated during site characterization. Effects that the area could experience from a repository project include demographic, economic, community service, fiscal, and social impacts. The Socioeconomic Site Study Plan is designed to provide a strategy to assess the potential for those impacts. The Socioeconomic Site Study Plan is structured to provide an overview of the socioeconomic program requirements, objectives, and activities to be conducted during site characterization. This report will describe the study design and its rationale; data collection, management, and reporting; program schedules and milestones; site study organization and management; and quality assurance issues. 43 refs

Ames expedited site characterization demonstration at the former manufactured gas plant site, Marshalltown, Iowa

International Nuclear Information System (INIS)

Bevolo, A.J.; Kjartanson, B.H.; Wonder, J.D.

1996-03-01

The goal of the Ames Expedited Site Characterization (ESC) project is to evaluate and promote both innovative technologies (IT) and state-of-the-practice technologies (SOPT) for site characterization and monitoring. In April and May 1994, the ESC project conducted site characterization, technology comparison, and stakeholder demonstration activities at a former manufactured gas plant (FMGP) owned by Iowa Electric Services (IES) Utilities, Inc., in Marshalltown, Iowa. Three areas of technology were fielded at the Marshalltown FMGP site: geophysical, analytical and data integration. The geophysical technologies are designed to assess the subsurface geological conditions so that the location, fate and transport of the target contaminants may be assessed and forecasted. The analytical technologies/methods are designed to detect and quantify the target contaminants. The data integration technology area consists of hardware and software systems designed to integrate all the site information compiled and collected into a conceptual site model on a daily basis at the site; this conceptual model then becomes the decision-support tool. Simultaneous fielding of different methods within each of the three areas of technology provided data for direct comparison of the technologies fielded, both SOPT and IT. This document reports the results of the site characterization, technology comparison, and ESC demonstration activities associated with the Marshalltown FMGP site. 124 figs., 27 tabs

Houdini: Site and locomotion analysis-driven design of an in-tank mobile cleanup robot

International Nuclear Information System (INIS)

Schempf, H.

1995-10-01

This paper describes design and locomotion analysis efforts to develop a new reconfigurable and collapsible working machine, dubbed Houdini, to remotely clean up hazardous-waste and petroleum storage tanks. The tethered robot system is designed to allow remote entry through man-way openings as small as 0.61 m in diameter, after which it expands its locomotors and opens up its collapsible backhoe/manipulator and plow to subsequently perform waste or material handling operations. The design is optimized to meet stringent site and safety requirements, and represents a viable alternative to (1) the long-reach manipulation systems proposed for hazardous storage tank cleanup, and (2) confined-entry manual cleanup approaches. The system development has been funded to provide waste mobilization and removal solutions for the hazardous waste storage tanks in the Department of Energy (DoE) Fernald and Oak Ridge complexes. Other potential applications areas are the cleanup of heavy-crude petroleum storage tanks. The author has developed a fully operational prototype which is currently undergoing testing

Site Study Plan for laboratory soil mechanics, Deaf Smith County site, Texas: Revision 1

International Nuclear Information System (INIS)

1987-12-01

This Site Study Plan for laboratory soil mechanics describes the laboratory testing to be conducted on soil samples collected as part of the characterization of the Deaf Smith County site, Texas. This study provides for measurements of index, mechanical, thermal, hydrologic, chemical, and mineral properties of soils from boring throughout the site. Samples will be taken from Playa Borings/Trenching, Transportation/Utilities Foundation Borings, Repository Surface Facilities Design Foundation Borings, and Exploratory Shaft Facilities Design Foundation Borings. Data from the laboratory tests will be used for soil strata characterization, design of foundations for surface structures, design of transportation facilities and utility structures, design of impoundments, design of shaft lining, design of the shaft freeze wall, shaft permitting, performance assessment calculations, and other program requirements. A tentative testing schedule and milestone log are given. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that appropriate documentation is maintained. 18 refs., 6 figs., 3 tabs

A thick homogeneous vegetated cover design proves cost - and schedule-effective for the reclamation of uranium mills sites near Spokane, Washington

Energy Technology Data Exchange (ETDEWEB)

Blacklaw, J.; Robertson, G.; Stoffel, D.; Ahmad, J.; Fordham, E. [Washington State Dept. of Health, Olympia, WA (United States)] [and others

1997-08-01

The Washington State Department of Health (WDOH) has licensed two medium sized uranium mills with tailings impoundments covering 28 and 40 hectares (70 and 100 acres), respectively, The uranium mill licensees have submitted closure and reclamation plans to the state, and site-specific conditions have determined the closure design features, Conventional uranium mill cover designs usually incorporate an overall cap of one to three meters, which includes a low-permeability clay barrier layer. A technical evaluation of several uranium mill facilities that used this design was published in the fall of 1994 and reported that unexpected vegetation root damage had occurred in the low-permeability clay (or bentonite amended) barrier layers. The technical report suggested that the low-permeability design feature at some sites could be compromised within a very short time and the regulatory goal of 1,000 years performance might not be achieved. In October 1994, WDOH sponsored a technical forum meeting to consider design alternatives to address these reliability concerns. Representatives from the federal government, nuclear industry, licensees, engineering firms, and state regulatory agencies attended the workshop. Risk factors considered in the evaluation of the uranium mill reclamation plans include: (1) radon gas emanation through the cover (the air pathway), and (2) migration of hazardous and/or radioactive constituents (the groundwater pathway). Additional design considerations include site structural stability, longevity of 1,000 years, and no active (ongoing) maintenance. 9 refs.

Site characterization plan:

International Nuclear Information System (INIS)

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in acordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and eveloping a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing prinicples, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed. 880 refs., 130 figs., 25 tabs

Elucidating the design principles of photosynthetic electron-transfer proteins by site-directed spin labeling EPR spectroscopy.

Science.gov (United States)

Ishara Silva, K; Jagannathan, Bharat; Golbeck, John H; Lakshmi, K V

2016-05-01

Site-directed spin labeling electron paramagnetic resonance (SDSL EPR) spectroscopy is a powerful tool to determine solvent accessibility, side-chain dynamics, and inter-spin distances at specific sites in biological macromolecules. This information provides important insights into the structure and dynamics of both natural and designed proteins and protein complexes. Here, we discuss the application of SDSL EPR spectroscopy in probing the charge-transfer cofactors in photosynthetic reaction centers (RC) such as photosystem I (PSI) and the bacterial reaction center (bRC). Photosynthetic RCs are large multi-subunit proteins (molecular weight≥300 kDa) that perform light-driven charge transfer reactions in photosynthesis. These reactions are carried out by cofactors that are paramagnetic in one of their oxidation states. This renders the RCs unsuitable for conventional nuclear magnetic resonance spectroscopy investigations. However, the presence of native paramagnetic centers and the ability to covalently attach site-directed spin labels in RCs makes them ideally suited for the application of SDSL EPR spectroscopy. The paramagnetic centers serve as probes of conformational changes, dynamics of subunit assembly, and the relative motion of cofactors and peptide subunits. In this review, we describe novel applications of SDSL EPR spectroscopy for elucidating the effects of local structure and dynamics on the electron-transfer cofactors of photosynthetic RCs. Because SDSL EPR Spectroscopy is uniquely suited to provide dynamic information on protein motion, it is a particularly useful method in the engineering and analysis of designed electron transfer proteins and protein networks. This article is part of a Special Issue entitled Biodesign for Bioenergetics--the design and engineering of electronic transfer cofactors, proteins and protein networks, edited by Ronald L. Koder and J.L. Ross Anderson. Copyright © 2016. Published by Elsevier B.V.

Site study plan for Transportation, Deaf Smith County Site, Texas: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

This site study plan describes transportation field studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. The studies are needed to identify and assess potential project impacts to transportation infrastructure and systems in the project vicinity and along potential transportation routes to the site across the State of Texas. The studies are also needed to locate and design project transportation facilities, and to evaluate and design impact mitigation. After identifying the transportation information requirements needed to comply with Federal, State, and local regulations and repository program requirements, the site study plan describes the study design and rationale, the field data collection procedures and equipment, the data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs for the characterization of site vicinity rail corridors and highway corridors, characterization of alternative statewide transportation routes, monitoring of site characterization effects on transportation, characterization of aircraft overflight patterns and hazardous material transportation patterns, and assessment of emergency response preparedness along alternative statewide transportation routes. 34 refs., 10 figs., 2 tabs

The development of quality management techniques in civil engineering design and site supervision

International Nuclear Information System (INIS)

Cowan, A.J.

1991-01-01

Quality assurance techniques have developed considerably over the past few years, and in particular the application of Quality Management within a service industry such as civil engineering has evolved into a well developed management control system. James Williamson and Partners were the first members of the Association of Consulting Engineers successfully to achieve third party accreditation with BSI for civil and structural design. The initial system was generated for work on Torness Power Station in the early 1980s, and the firm has, in the last ten years, developed a flexible quality system to effectively control and co-ordinate complex projects. This paper discusses the use of quality assurance (QA) techniques in a civil engineering design office, looking at a few areas where the requirements of BS 5750 and BS 5882 are difficult to interpret. Some observations are also made on the adoption of QA for site supervision. (author)

Functional Complexity and Web Site Design : Evaluating the Online Presence of UNESCO World Heritage Sites

NARCIS (Netherlands)

De Jong, Menno D.T.; Wu, Yuguang

2018-01-01

Functional complexity is a widespread and underresearched phenomenon in Web sites. This article explores a specific case of functional complexity by analyzing the content of UNESCO World Heritage Web sites, which have to meet demands from both World Heritage and tourism perspectives. Based on a

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado

International Nuclear Information System (INIS)

1992-10-01

Diffusion coefficients for radon gas in earthen materials are required to design suitable radon-barrier covers for uranium tailings impoundments and other materials that emit radon gas. Many early measurements of radon diffusion coefficients relied on the differences in steady-state radon fluxes measured from radon source before and after installation of a cover layer of the material being tested. More recent measurements have utilized the small-sample transient (SST) technique for greater control on moistures and densities of the test soils, greater measurement precision, and reduced testing time and costs. Several of the project sites for the US Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Program contain radiologically contaminated subsurface material composed predominantly of cobbles, gravels andsands. Since remedial action designs require radon diffusion coefficients for the source materials as well as the cover materials, these cobbly and gravelly materials also must be tested. This report contains the following information: a description of the test materials used and the methods developed to conduct the SST radon diffusion measurements on cobbly soils; the protocol for conducting radon diffusion tests oncobbly soils; the results of measurements on the test samples; and modifications to the FITS computer code for analyzing the time-dependent radon diffusion data

User-Interface Design Characteristics of Fortune 500 B2C E-Commerce Sites and Industry Differences

Science.gov (United States)

Zhao, Jensen J.; Truell, Allen D.; Alexander, Melody W.

2006-01-01

This study examined the user-interface design characteristics of 107 Fortune 500 B2C e-commerce Web sites and industry differences. Data were collected from corporate homepages, B2C product/service pages, B2C interactive shopping pages, as well as customer satisfaction of 321 online shoppers. The findings indicate that (a) to attract online…

Influence of site on thermal design of a two floor ZEH in the desert

KAUST Repository

Serag-Eldin, M. A.

2010-12-01

The paper presents the results of investigating the effect of Latitude angle and environmental temperature on the thermal behavior and performance of a fully equipped, air-conditioned, zero energy house located in a desert residential compound. It makes use of the thermal design and analysis tools presented in other work and extends the investigation to include different site environmental characteristics. Data from eight different meteorological sites in the KSA where considered. It is demonstrated that for the same house and occupancy profile, the PV modules, battery storage, and air-conditioning equipment requirements can differ markedly depending on local environment properties. During Summer and Spring the main heat load is due to cooling, but during winter season the load can vary from full cooling, to mixed cooling and heating, to even full heating; the heating load sometimes dictating the size of the required equipment. © 2010 IEEE.

Influence of site on thermal design of a two floor ZEH in the desert

KAUST Repository

Serag-Eldin, M. A.

2010-01-01

The paper presents the results of investigating the effect of Latitude angle and environmental temperature on the thermal behavior and performance of a fully equipped, air-conditioned, zero energy house located in a desert residential compound. It makes use of the thermal design and analysis tools presented in other work and extends the investigation to include different site environmental characteristics. Data from eight different meteorological sites in the KSA where considered. It is demonstrated that for the same house and occupancy profile, the PV modules, battery storage, and air-conditioning equipment requirements can differ markedly depending on local environment properties. During Summer and Spring the main heat load is due to cooling, but during winter season the load can vary from full cooling, to mixed cooling and heating, to even full heating; the heating load sometimes dictating the size of the required equipment. © 2010 IEEE.

Methodology for the elaboration of Natura 2000 sites designation acts in the Walloon Region (Belgium: calcareous grasslands in the Lesse-and-Lomme area

Directory of Open Access Journals (Sweden)

Mahy G.

2005-01-01

Full Text Available In the Walloon Region (Belgium, 239 sites have been selected to be included in the Natura 2000 network. The next step is to write designation acts in order to legally protect these 221,000 ha. In this pilot study, a designation act was elaborated for a Natura 2000 site of 2,569 ha and located in the Lesse-and-Lomme area within the Calestienne region. Although the site includes 40 ha of calcareous grasslands, characterised by an exceptional flora and fauna, this habitat is very threatened by abandonment and fragmentation.The methodology used to elaborate the designation act is presented with respect to calcareous grassland. Firstly, in spring and summer 2003, an accurate map of natural habitats was produced, with every single patch of calcareous grassland being mapped. Information was also collected in order to evaluate conservation status. Based on this information, conservation status was then assessed with respect to three different criteria: (1 integrity of the cortege species, (2 habitat structure and (3 degradations. Thirdly, the site was divided into objective zones according to the different habitats and species of Community interest found in the site. Hence, an objective zone was delineated for calcareous grasslands. This objective zone was then divided in several management units. Finally, at these different spatial levels (site, objective zone, management unit, management measures were suggested. As a result, in the draft designation act, the target is to maintain or restore 230 ha of calcareous grassland, instead of the existing 40 ha. This ambitious target requires large-scale restoration and an efficient grazing scheme. These will need important resources for their successful implementation

Remedial action and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado

International Nuclear Information System (INIS)

1993-07-01

The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (EPA, 1987). According to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 Public Law (PL) 95-604 (PL 95-604), the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined that for Slick Rock, this assessment shall include hydrogeologic site characterization for two separate uranium processing sites, the Union Carbide (UC) site and the North Continent (NC) site, and for the proposed Burro Canyon disposal site

Report of the Siting Policy Task Force

International Nuclear Information System (INIS)

1979-08-01

In August 1978, the Nuclear Regulatory Commission directed the staff to develop a general policy statement on nuclear power reactor siting. A Task Force was formed for that purpose and has prepared a statement of current NRC policy and practice and has recommended a number of changes to current policy. Recommendations were made to accomplish the following goals: (1) To strengthen siting as a factor in defense in depth by establishing requirements for site approval that are independent of plant design consideration. The present policy of permitting plant design features to compensate for unfavorable site characteristics has resulted in improved designs but has tended to deemphasize site isolation. (2) To take into consideration in siting the risk associated with accidents beyond the design basis (Class 9) by establishing population density and distribution criteria. Plant design improvements have reduced the probability and consequences of design basis accidents, but there remains the residual risk from accidents not considered in the design basis. Although this risk cannot be completely reduced to zero, it can be significantly reduced by selective siting. (3) To require that sites selected will minimize the risk from energy generation. The selected sites should be among the best available in the region where new generating capacity is needed. Siting requirements should be stringent enough to limit the residual risk of reactor operation but not so stringent as to eliminate the nuclear option from large regions of the country. This is because energy generation from any source has its associated risk, with risks from some energy sources being greater than that of the nuclear option

Designing artificial 2D crystals with site and size controlled quantum dots.

Science.gov (United States)

Xie, Xuejun; Kang, Jiahao; Cao, Wei; Chu, Jae Hwan; Gong, Yongji; Ajayan, Pulickel M; Banerjee, Kaustav

2017-08-30

Ordered arrays of quantum dots in two-dimensional (2D) materials would make promising optical materials, but their assembly could prove challenging. Here we demonstrate a scalable, site and size controlled fabrication of quantum dots in monolayer molybdenum disulfide (MoS 2 ), and quantum dot arrays with nanometer-scale spatial density by focused electron beam irradiation induced local 2H to 1T phase change in MoS 2 . By designing the quantum dots in a 2D superlattice, we show that new energy bands form where the new band gap can be controlled by the size and pitch of the quantum dots in the superlattice. The band gap can be tuned from 1.81 eV to 1.42 eV without loss of its photoluminescence performance, which provides new directions for fabricating lasers with designed wavelengths. Our work constitutes a photoresist-free, top-down method to create large-area quantum dot arrays with nanometer-scale spatial density that allow the quantum dots to interfere with each other and create artificial crystals. This technique opens up new pathways for fabricating light emitting devices with 2D materials at desired wavelengths. This demonstration can also enable the assembly of large scale quantum information systems and open up new avenues for the design of artificial 2D materials.

Epitope-based peptide vaccine design and target site depiction against Ebola viruses: an immunoinformatics study.

Science.gov (United States)

Khan, M A; Hossain, M U; Rakib-Uz-Zaman, S M; Morshed, M N

2015-07-01

Ebola viruses (EBOVs) have been identified as an emerging threat in recent year as it causes severe haemorrhagic fever in human. Epitope-based vaccine design for EBOVs remains a top priority because a mere progress has been made in this regard. Another reason is the lack of antiviral drug and licensed vaccine although there is a severe outbreak in Central Africa. In this study, we aimed to design an epitope-based vaccine that can trigger a significant immune response as well as to prognosticate inhibitor that can bind with potential drug target sites using various immunoinformatics and docking simulation tools. The capacity to induce both humoral and cell-mediated immunity by T cell and B cell was checked for the selected protein. The peptide region spanning 9 amino acids from 42 to 50 and the sequence TLASIGTAF were found as the most potential B and T cell epitopes, respectively. This peptide could interact with 12 HLAs and showed high population coverage up to 80.99%. Using molecular docking, the epitope was further appraised for binding against HLA molecules to verify the binding cleft interaction. In addition with this, the allergenicity of the epitopes was also evaluated. In the post-therapeutic strategy, docking study of predicted 3D structure identified suitable therapeutic inhibitor against targeted protein. However, this computational epitope-based peptide vaccine designing and target site prediction against EBOVs open up a new horizon which may be the prospective way in Ebola viruses research; the results require validation by in vitro and in vivo experiments. © 2015 John Wiley & Sons Ltd.

The Concept of Historical Landscape Design at Watugong Archaeological Site Area in Malang City

Science.gov (United States)

Setyabudi, I.; Alfian, R.; Hastutiningtyas, W. R.

2017-10-01

Malang city has the high historical value. It showed by many archaeological situses found, such as: The Dutch Colonial Building until kingdom era on classical history period. Generally, it could be seen at urban affairs like government building even the ancient house. But the last kingdom archaeological site only found at the village. The oldest archaeological site in Malang city was found on Kanjuruhan Kingdom, which is concentrated in Tlogomas. The Watu Gong Hamlet that was located in Tlogomas Political District had an archaeological site. It was a big stone in which the stone looked like a traditional music instrument, it was called Gong. As the archaeological site in megalithicum, before the Hindu and Budha came in from India, that stone was predicted as the foundation structure of the big building. The Watu Gong Hamlet was located in Tlogomas archeological site area, also Merjosari and Karang Besuki. Three of them are the archeological sites for Kanjuruhan Kingdom at eigth century, until Kahuripan Kingdom around the eleventh century, as the heir of the Ancient Mataram Kingdom. The urban government has a program to improve the village required to their region potential and it was possible to revitalize the Tlogomas village, so that the historical character can be seen well. The modernity of a hamlet has impact on the local identity blured. In which, they did not think about economic only and it can be minimized, also the hamlet will be a characterized tourism object. The revitalization purposed to continuing the past, then it’s connected to present. It’s performed as corridored garden planning. The landscape development appropriated to promote about the characters of Kacapiring flower, Rose, Jasmine and Puring. They are the special plants from Kanjuruhan Kingdom, beside the other furniture street model. This research was descriptive explorative and discussed about the concept with architecture design approach, started from data collecting, precedent study

Geochemical investigation of UMTRAP designated site at Durango, Colorado

International Nuclear Information System (INIS)

Markos, G.; Bush, K.J.

1983-09-01

This report is the result of a geochemical investigation of the former uranium mill and tailings site at Durango, Colorado. This is one in a series of site specific geochemical investigations performed on the inactive uranium mill tailings included in the UMTRA Project. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results will be used to model contaminant migration and to develop criteria for long-term containment media such as a cover system which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. The solid samples are water extracted remove easily soluble salts and acids extracted to remove cabonates and hydroxides. The water extracts and solid samples were analyzed for the major and trace elements. A limited number of samples were analyzed for radiological components. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Three major conclusions are: (1) carbonate salts and low TDS characterize the tailings; (2) the adjacent area and raffinate ponds contain contaminants deposited by a single event of fluid permeation of the soils; and (3) the Animas River adjacent to the site has elevated gross alpha activity attributed to 226 Ra in the sediments derived from the tailings or milling activities

Implications of next generation attenuation ground motion prediction equations for site coefficients used in earthquake resistant design

Science.gov (United States)

Borcherdt, Roger D.

2014-01-01

Proposals are developed to update Tables 11.4-1 and 11.4-2 of Minimum Design Loads for Buildings and Other Structures published as American Society of Civil Engineers Structural Engineering Institute standard 7-10 (ASCE/SEI 7–10). The updates are mean next generation attenuation (NGA) site coefficients inferred directly from the four NGA ground motion prediction equations used to derive the maximum considered earthquake response maps adopted in ASCE/SEI 7–10. Proposals include the recommendation to use straight-line interpolation to infer site coefficients at intermediate values of (average shear velocity to 30-m depth). The NGA coefficients are shown to agree well with adopted site coefficients at low levels of input motion (0.1 g) and those observed from the Loma Prieta earthquake. For higher levels of input motion, the majority of the adopted values are within the 95% epistemic-uncertainty limits implied by the NGA estimates with the exceptions being the mid-period site coefficient, Fv, for site class D and the short-period coefficient, Fa, for site class C, both of which are slightly less than the corresponding 95% limit. The NGA data base shows that the median value  of 913 m/s for site class B is more typical than 760 m/s as a value to characterize firm to hard rock sites as the uniform ground condition for future maximum considered earthquake response ground motion estimates. Future updates of NGA ground motion prediction equations can be incorporated easily into future adjustments of adopted site coefficients using procedures presented herein. 

Implications of NGA for NEHRP site coefficients

Science.gov (United States)

Borcherdt, Roger D.

2012-01-01

Three proposals are provided to update tables 11.4-1 and 11.4-2 of Minimum Design Loads for Buildings and Other Structures (7-10), by the American Society of Civil Engineers (2010) (ASCE/SEI 7-10), with site coefficients implied directly by NGA (Next Generation Attenuation) ground motion prediction equations (GMPEs). Proposals include a recommendation to use straight-line interpolation to infer site coefficients at intermediate values of ̅vs (average shear velocity). Site coefficients are recommended to ensure consistency with ASCE/SEI 7-10 MCER (Maximum Considered Earthquake) seismic-design maps and simplified site-specific design spectra procedures requiring site classes with associated tabulated site coefficients and a reference site class with unity site coefficients. Recommended site coefficients are confirmed by independent observations of average site amplification coefficients inferred with respect to an average ground condition consistent with that used for the MCER maps. The NGA coefficients recommended for consideration are implied directly by the NGA GMPEs and do not require introduction of additional models.

41 CFR 102-76.55 - What sustainable development principles must Federal agencies apply to the siting, design, and...

Science.gov (United States)

2010-07-01

... and Construction Sustainable Development § 102-76.55 What sustainable development principles must... Acquisition,” Federal agencies must apply sustainable development principles to the siting, design, and... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false What sustainable...

From heat integration targets toward implementation – A TSA (total site analysis)-based design approach for heat recovery systems in industrial clusters

International Nuclear Information System (INIS)

Hackl, Roman; Harvey, Simon

2015-01-01

The European process industry is facing major challenges to decrease production costs. One strategy to achieve this is by increasing energy efficiency. Single chemical processes are often well-integrated and the tools to target and design such measures are well developed. Site-wide heat integration based on total site analysis tools can be used to identify opportunities to further increase energy efficiency. However, the methodology has to be developed further in order to enable identification of practical heat integration measures in a systematic way. Designing site-wide heat recovery systems across an industrial cluster is complex and involves aspects apart from thermal process and utility flows. This work presents a method for designing a roadmap of heat integration investments based on total site analysis. The method is applied to a chemical cluster in Sweden. The results of the case study show that application of the proposed method can achieve up to 42% of the previously targeted hot utility savings of 129 MW. A roadmap of heat integration systems is suggested, ranging from less complex systems that achieve a minor share of the heat recovery potential to sophisticated, strongly interdependent systems demanding large investments and a high level of collaboration. - Highlights: • Methodology focused on the practical implementation of site-wide heat recovery. • Algorithm to determine a roadmap of heat integration investments. • Case study: 42% hot utility savings potential at a pay-back period of 3.9y.

Site investigations, design, construction, operation, shutdown and surveillance of repositories for low- and intermediate-level radioactive wastes in rock cavities

International Nuclear Information System (INIS)

1984-01-01

The report provides an overview and technical guidelines for considerations and for activities to be undertaken for safety assessment, site investigations, design, construction, operation, shutdown and surveillance of repositories for the disposal of low- and intermediate-level radioactive wastes in rock cavities. A generalized sequence of investigations is introduced which proceeds through region and site selection to the stage where the site is confirmed by detailed geoscientific investigations as being suitable for a waste repository. The different procedures and somewhat specific investigative needs with respect to existing mines are dealt with separately. General design, as well as specific requirements with respect to the different stages of design and construction, are dealt with. A review of activities related to the operational and post-operational stages of repositories in rock cavities is presented. The report describes in general terms the procedures related to different stages of disposal operation; also the conditions for shutdown together with essential shutdown and sealing activities and the related safety assessment requirements. Guidance is also given on the surveillance programme which will allow for inspection, testing, maintenance and security of a disposal facility during the operational phase, as well as for the post-operational stage for periods determined as necessary by the national authorities

Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project

Energy Technology Data Exchange (ETDEWEB)

MacDougall, H R; Scully, L W; Tillerson, J R [comps.

1987-09-01

The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O.

Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project

International Nuclear Information System (INIS)

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R.

1987-09-01

The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lakeview, Oregon: Volume 1, Text and appendices A through D

International Nuclear Information System (INIS)

Chernoff, A.R.

1992-07-01

The Lakeview inactive uranium processing site is in Lake County, Oregon, approximately one mile northwest of the town of Lakeview, sixteen miles north of the California-Oregon border, and 96 miles east of Klamath Falls. The total designated site covers an area of 258 acres consisting of a tailings pile (30 acres). seven evaporation ponds (69 acres), the mill buildings, and related structures. The mill buildings and other structures have been decontaminated and are currently being used by Goose Lake Lumber Company. The tailings pile at the processing site was originally stabilized by Atlantic Richfield with an earthen cover 18--24 inches thick. The average depth of the tailings, including the cover, varied from six to eight feet. There were estimated to be 662,000 cubic yards of tailings, windblown contaminated materials, and vicinity property materials. During remedial action under the Uranium Mill Tailings Remedial Action (UMTRA) Project, approximately 264,000 cubic yards of additional contaminated materials were identified from excavations required to remove thorium- and arsenic-contaminated soils. The remedial action for the Lakeview site consisted of the cleanup, relocation, consolidation, and stabilization of all residual radioactive materials and thorium- and arsenic-contaminated materials in a partially below-grade disposal cell at a location approximately seven miles northwest of the tailings site, identified as the Collins Ranch site. A cover, including a radon/infiltration barrier and rock layer for protection from erosion, was Placed on top of the tailings. A rock-soil matrix covers the topslope and provides a growth medium for vegetation. The US Department of Energy (DOE) will retain the license and surveillance and maintenance responsibilities for the final restricted site of 13 acres

Mobile hot cell transition design phase study for radioactive waste treatment on the Hanford reservation site

International Nuclear Information System (INIS)

Pons, Y.

2010-01-01

shipped to BNF number 164, named CEDRA on Cadarache site (in operation in 2009). AREVA TA (ATA) is pleased to provide AREVA Federal Services (AFS) a phased plan to provide an Adaptation Design Technical Report and Organization. This approach will facilitate the assessment of the Final design Phase (After September 2010) and funding to support the engineering, procurement, and construction planning leading to the fabrication of a Mobile Hot Cell (MHC). (author)

Proposal for the award of two contracts for the provision of mechanical design and draughting services on and off the CERN Site

CERN Document Server

2006-01-01

This document concerns the award of two contracts for the provision of mechanical design and draughting services on and off the CERN site. The Finance Committee is invited to agree to the negotiation of two contracts with: 1. ACROTECNA (FR), the lowest bidder, for approximately 55% of the provision of mechanical design and draughting services on and off the CERN site, for a period of three years for a total amount not exceeding 794 200 euros (1 239 006 Swiss francs), not subject to revision. The contract will include options for two one-year extensions beyond the initial three-year period. The rate of exchange used is that stipulated in the tender. 2. TECNICAS AERONAUTICAS MADRID (ES), the joint lowest bidder after alignment, for approximately 45% of the provision of mechanical design and draughting services on and off the CERN site, for a period of three years for a total amount not exceeding 1 013 730 Swiss francs, not subject to revision. The contract will include options for two one-year extensions beyond...

77 FR 63312 - Notice of Intent: Designation of an Ocean Dredged Material Disposal Site (ODMDS) in Eastern Long...

Science.gov (United States)

2012-10-16

... Material Disposal Site (ODMDS) in Eastern Long Island Sound; Connecticut, New York, and Rhode Island AGENCY... (ODMDS) to serve the eastern Long Island Sound region (Connecticut, New York, and Rhode Island). SUMMARY... Environmental Impact Statement that supported the designation of the Central and Western Long Island Sound...

Design basis flood for nuclear power plants on river sites

International Nuclear Information System (INIS)

1983-01-01

The Guide presents techniques for determining the design basis flood (DBF) to be used for siting nuclear power plants at or near non-tidal reaches of rivers and for protecting nuclear power plants against floods. Since flooding of a nuclear power plant can have repercussions on safety, the DBF is always chosen to have a very low probability of exceedance per annum. The DBF may result from one or more of the following causes: (1) Precipitation, snowmelt; (2) Failure of water control structures, either from seismic or hydrological causes or from faulty operation of these structures; (3) Channel obstruction such as landslide, ice effects, log or debris jams, and effects of vulcanism. Normally the DBF is not less than any recorded or historical flood occurrence. For flood evaluation two types of methods are discussed in this Guide: probabilistic and deterministic. Simple probabilistic methods to determine floods of such low exceedance probability have a great degree of uncertainty and are presented for use only during the site survey. However, the more sophisticated probabilistic methods, the so-called stochastic methods, may give an acceptable result, as outlined in this Guide. The preferred method of evaluating the component of the DBF due to precipitation, as described in this Guide, is the deterministic one, based on the concept of a limit to the probable maximum precipitation (PMP) and on the unit hydrograph technique. Dam failures may generate a flood substantially more severe than that due to precipitation. The methodology for evaluating these types of floods is therefore presented in this Guide. Making allowance for the possible simultaneous occurrence of two or more important flood-producing events is also discussed here. The Guide does not deal with floods caused by sabotage

Intra-site Secure Transport Vehicle test and evaluation

International Nuclear Information System (INIS)

Scott, S.

1995-01-01

In the past many DOE and DoD facilities involved in handling nuclear material realized a need to enhance the safely and security for movement of sensitive materials within their facility, or ''intra-site''. There have been prior efforts to improve on-site transportation; however, there remains a requirement for enhanced on-site transportation at a number of facilities. The requirements for on-site transportation are driven by security, safety, and operational concerns. The Intra-site Secure Transport Vehicle (ISTV) was designed to address these concerns specifically for DOE site applications with a standardized vehicle design. This paper briefly reviews the ISTV design features providing significant enhancement of onsite transportation safety and security, and also describes the test and evaluation activities either complete of underway to validate the vehicle design and operation

Nuclear power: Siting and safety

International Nuclear Information System (INIS)

Openshaw, S.

1986-01-01

By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

Design, Modeling, and CFD Analysis of a Micro Hydro Pelton Turbine Runner: For the Case of Selected Site in Ethiopia

Directory of Open Access Journals (Sweden)

Tilahun Nigussie

2017-01-01

Full Text Available This paper addresses the design, modeling, and performance analysis of a Pelton turbine using CFD for one of the selected micro hydro potential sites in Ethiopia to meet the requirements of the energy demands. The site has a net head of 47.5 m and flow rate of 0.14 m3/s. The design process starts with the design of initial dimensions for the runner based on different literatures and directed towards the modeling of bucket using CATIA V5. The performance of the runner has been analyzed in ANSYS CFX (CFD under given loading conditions of the turbine. Consequently, the present study has also the ambition to reduce the size of the runner to have a cost effective runner design. The case study described in this paper provides an example of how the size of turbine can affect the efficiency of the turbine. These were discussed in detail which helps in understanding of the underlying fluid dynamic design problem as an aid for improving the efficiency and lowering the manufacturing cost for future study. The result showed that the model is highly dependent on the size and this was verified and discussed properly using flow visualization of the computed flow field and published result.

Development of in-structure design spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site

International Nuclear Information System (INIS)

Julyk, L.J.

1995-09-01

In-structure response spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site are developed on the basis of recent soil-structure-interaction analyses. Recommended design spectra are provided for various locations on the tank dome

Design and fabrication of a low-cost Darrieus vertical-axis wind-turbine system, phase 2. Volume 3: Design, fabrication, and site drawing

Science.gov (United States)

1983-03-01

The design, fabrication, and site drawings associated with fabrication, installation, and check out of 100 kW 17 meter Vertical Axis Wind Turbines (VAWTs) were reported. The turbines are Darrieus type VAWTs with rotors 17 meters in diameter and 25.15 meters in height. They can produce 100 kW of electric power at a cost of energy as low as 3 cents per kWh, in an 18 mph wind regime using 12% annualized costs. Four turbines are produced, three are installed and operable.

Remedial design process for Montclair/West Orange and Glen Ridge radium sites

International Nuclear Information System (INIS)

MacIndoe, M.; Johnson, R.; Paez-Restrepo, A.; Wilkinson, S.; Hyman, M.

1994-01-01

The Montclair/West Orange and Glen Ridge Superfund Sites, located in Essex County, New Jersey, are contaminated to varying degrees with radioactive materials. The waste materials originated from radium processing facilities prevalent in the area during the early 1900's. The two sites consist of 769 residential and commercial properties having a combined land area of approximately 210 acres. Historically, radioactive waste materials were disposed as landfill material in what were once rural areas. As development flourished, homes and streets were constructed over the landfilled waste. In 1981 the EPA conducted an aerial gamma radiation survey of the area to determine the presence of radioactive materials. It was from this survey that subsequent ground studies where initiated, and elevated gamma radiation and radon levels were discovered. The paper will discuss the methods used to obtain data through field investigations; the relationship between the interpretation of data to define the vertical and lateral limits of contamination and the selection of remedial design methods used to develop excavation plans; the evolution of remediation methods and technologies relative to the remediation of structures by underpinning basements, on-grade structures, and chimneys; removal of contaminated material beneath footings without cribbing; and demolition of basement foundation walls (where contaminated) without use of traditional support methods. Finally, the paper will discuss remedial action execution of the work

Confidence assessment. Site-descriptive modelling SDM-Site Laxemar

International Nuclear Information System (INIS)

2009-06-01

The objective of this report is to assess the confidence that can be placed in the Laxemar site descriptive model, based on the information available at the conclusion of the surface-based investigations (SDM-Site Laxemar). In this exploration, an overriding question is whether remaining uncertainties are significant for repository engineering design or long-term safety assessment and could successfully be further reduced by more surface-based investigations or more usefully by explorations underground made during construction of the repository. Procedures for this assessment have been progressively refined during the course of the site descriptive modelling, and applied to all previous versions of the Forsmark and Laxemar site descriptive models. They include assessment of whether all relevant data have been considered and understood, identification of the main uncertainties and their causes, possible alternative models and their handling, and consistency between disciplines. The assessment then forms the basis for an overall confidence statement. The confidence in the Laxemar site descriptive model, based on the data available at the conclusion of the surface based site investigations, has been assessed by exploring: - Confidence in the site characterization data base, - remaining issues and their handling, - handling of alternatives, - consistency between disciplines and - main reasons for confidence and lack of confidence in the model. Generally, the site investigation database is of high quality, as assured by the quality procedures applied. It is judged that the Laxemar site descriptive model has an overall high level of confidence. Because of the relatively robust geological model that describes the site, the overall confidence in the Laxemar Site Descriptive model is judged to be high, even though details of the spatial variability remain unknown. The overall reason for this confidence is the wide spatial distribution of the data and the consistency between

Confidence assessment. Site-descriptive modelling SDM-Site Laxemar

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

The objective of this report is to assess the confidence that can be placed in the Laxemar site descriptive model, based on the information available at the conclusion of the surface-based investigations (SDM-Site Laxemar). In this exploration, an overriding question is whether remaining uncertainties are significant for repository engineering design or long-term safety assessment and could successfully be further reduced by more surface-based investigations or more usefully by explorations underground made during construction of the repository. Procedures for this assessment have been progressively refined during the course of the site descriptive modelling, and applied to all previous versions of the Forsmark and Laxemar site descriptive models. They include assessment of whether all relevant data have been considered and understood, identification of the main uncertainties and their causes, possible alternative models and their handling, and consistency between disciplines. The assessment then forms the basis for an overall confidence statement. The confidence in the Laxemar site descriptive model, based on the data available at the conclusion of the surface based site investigations, has been assessed by exploring: - Confidence in the site characterization data base, - remaining issues and their handling, - handling of alternatives, - consistency between disciplines and - main reasons for confidence and lack of confidence in the model. Generally, the site investigation database is of high quality, as assured by the quality procedures applied. It is judged that the Laxemar site descriptive model has an overall high level of confidence. Because of the relatively robust geological model that describes the site, the overall confidence in the Laxemar Site Descriptive model is judged to be high, even though details of the spatial variability remain unknown. The overall reason for this confidence is the wide spatial distribution of the data and the consistency between

Novel implant design improves implant survival in multirooted extraction sites: a preclinical pilot study.

Science.gov (United States)

Sivan-Gildor, Adi; Machtei, Eli E; Gabay, Eran; Frankenthal, Shai; Levin, Liran; Suzuki, Marcelo; Coelho, Paulo G; Zigdon-Giladi, Hadar

2014-10-01

The primary aim is to evaluate clinical, radiographic, and histologic parameters of novel implants with "three roots" design that were inserted into fresh multirooted extraction sockets. A secondary aim is to compare this new implant to standard root-form dental implants. Immediate implantation of novel or standard design 6 × 6-mm implants was performed bilaterally into multirooted sockets in mandibles of mini-pigs. Twelve weeks later, clinical, radiographic, stability, histomorphometric, and microcomputed tomography (micro-CT) analyses were performed. Survival rates were significantly higher in the test implants compared with control (92.8% versus 33.3%, respectively; P micro-CT analyses demonstrated bone fill in the inner part of the test implants. Moreover, bone-to-implant contact was higher in the test implants (55.50% ± 3.68% versus 42.47% ± 9.89%). Contrary to the clinical, radiographic, and histomorphometric results, resonance frequency analysis measurements were greater in the control group (77.74 ± 3.21 implant stability quotient [ISQ]) compared with the test group (31.09 ± 0.28 ISQ), P = 0.008. The novel design implants resulted in significantly greater survival rate in multirooted extraction sites. Further studies will be required to validate these findings.

Evaluation of Landfill Cover Design Options for Waste Disposal Sites in the Coastal Regions of Ghana

Directory of Open Access Journals (Sweden)

Kodwo Beedu Keelson

2015-01-01

Full Text Available Uncontrolled leachate generation from operational and closed waste disposal sites is a major environmental concern in the coastal regions of Ghana which have abundant surface water and groundwater resources. The Ghana Landfill Guidelines requires the provision of a final cover or capping system as part of a final closure plan for waste disposal sites in the country as a means of minimizing the harmful environmental effects of these emissions. However, this technical manual does not provide explicit guidance on the material types or configuration for landfill covers that would be suitable for the different climatic conditions in the country. Four landfill cover options which are based on the USEPA RCRA-type and evapotranspirative landfill cover design specifications were evaluated with the aid of the HELP computer program to determine their suitability for waste disposal sites located in the Western, Central and Greater Accra regions. The RCRA Subtitle C cover which yielded flux rates of less than 0.001 mm/yr was found to be suitable for the specific climatic conditions. The RCRA Subtitle D cover was determined to be unsuitable due to the production of very large flux rates in excess of 200 mm/yr. The results for the anisotropic barrier and capillary barrier covers were inconclusive. Recommendations for further study include a longer simulation period as well the study of the combined effects of different topsoil vegetative conditions and evaporative zone depths on the landfill water balance. The use of other water balance models such as EPIC, HYDRUS-2D and UNSAT-H for the evaluation of the evapotranspirative landfill cover design options should also be considered.

In vitro results of flexible light-emitting antimicrobial bandage designed for prevention of surgical site infections

Science.gov (United States)

Greenberg, Mitchell; Sharan, Riti; Galbadage, Thushara; Sule, Preeti; Smith, Robert; Lovelady, April; Cirillo, Jeffrey D.; Glowczwski, Alan; Maitland, Kristen C.

2018-02-01

Surgical site infections (SSIs) are a leading cause of morbidity and mortality and a significant expense to the healthcare system and hospitals. The majority of these infections are preventable; however, increasing bacterial resistance, biofilm persistence, and human error contribute to the occurrence of these healthcare-associated infections. We present a flexible antimicrobial blue-light emitting bandage designed for use on postoperative incisions and wounds. The photonic device is designed to inactivate bacteria present on the skin and prevent bacterial colonization of the site, thus reducing the occurrence of SSIs. This antimicrobial light emitting bandage uses blue light's proven abilities to inactivate a wide range of clinical pathogens regardless of their resistance to antibiotics, inactivate bacteria without harming mammalian cells, improve wound healing, and inactivate bacteria in biofilms. The antimicrobial bandage consists of a thin 2"x2" silicone sheet with an array of 77 LEDs embedded in multiple layers of the material for thermal management. The 405 nm center wavelength LED array is designed to be a wearable device that integrates with standard hospital infection prevention protocols. The device was characterized for irradiance of 44.5 mW/cm2. Methicillin-resistant Staphylococcus aureus seeded in a petri dish was used to evaluate bacterial inactivation in vitro. Starting with a concentration of 2.16 x 107 colony forming units (CFU)/mL, 45% of the bacteria was inactivated within 15 minutes, 65% had been inactivated by 30 minutes, 99% was inactivated by 60 minutes, and a 7 log reduction and complete sterilization was achieved within 120 minutes.

Drift design methodology and preliminary application for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Hardy, M.P.; Bauer, S.J.

1991-12-01

Excavation stability in an underground nuclear waste repository is required during construction, emplacement, retrieval (if required), and closure phases to ensure worker health and safety, and to prevent development of potential pathways for radionuclide migration in the post-closure period. Stable excavations are developed by appropriate excavation procedures, design of the room shape, design and installation of rock support reinforcement systems, and implementation of appropriate monitoring and maintenance programs. In addition to the loads imposed by the in situ stress field, the repository drifts will be impacted by thermal loads developed after waste emplacement and, periodically, by seismic loads from naturally occurring earthquakes and underground nuclear events. A priori evaluation of stability is required for design of the ground support system, to confirm that the thermal loads are reasonable, and to support the license application process. In this report, a design methodology for assessing drift stability is presented. This is based on site conditions, together with empirical and analytical methods. Analytical numerical methods are emphasized at this time because empirical data are unavailable for excavations in welded tuff either at elevated temperatures or under seismic loads. The analytical methodology incorporates analysis of rock masses that are systematically jointed, randomly jointed, and sparsely jointed. In situ thermal and seismic loads are considered. Methods of evaluating the analytical results and estimating ground support requirements for all the full range of expected ground conditions are outlines. The results of a preliminary application of the methodology using the limited available data are presented. 26 figs., 55 tabs

VS30 – A site-characterization parameter for use in building Codes, simplified earthquake resistant design, GMPEs, and ShakeMaps

Science.gov (United States)

Borcherdt, Roger D.

2012-01-01

VS30, defined as the average seismic shear-wave velocity from the surface to a depth of 30 meters, has found wide-spread use as a parameter to characterize site response for simplified earthquake resistant design as implemented in building codes worldwide. VS30 , as initially introduced by the author for the US 1994 NEHRP Building Code, provides unambiguous definitions of site classes and site coefficients for site-dependent response spectra based on correlations derived from extensive borehole logging and comparative ground-motion measurement programs in California. Subsequent use of VS30 for development of strong ground motion prediction equations (GMPEs) and measurement of extensive sets of VS borehole data have confirmed the previous empirical correlations and established correlations of SVS30 with VSZ at other depths. These correlations provide closed form expressions to predict S30 V at a large number of additional sites and further justify S30 V as a parameter to characterize site response for simplified building codes, GMPEs, ShakeMap, and seismic hazard mapping.

Heritage planning and rethinking the meaning and values of designating heritage sites in a post-disaster context: The case of Aceh, Indonesia

Science.gov (United States)

Meutia, Z. D.; Akbar, R.; Zulkaidi, D.

2018-05-01

Heritage has become a driver of development as stated in the New Urban Agenda 2016 report. A starting premise of most recent studies of the concept of heritage suggests that its nature is not as a static inheritance with fixed and enduring values. Rather, the identification of sites as heritage requires a process of identification, or heritage creation. Heritage is a fluid phenomenon rather than a static set of objects or sites with fixed meanings. This paper uses theory from Smith [1] who argued that there is no such thing as a heritage; heritage is essentially a cultural custom and social process. Today, site-based heritage planning only considers the values of old towns and lacks clarity in terms of values that create criteria for the designation of cultural heritage sites in another context. Yet, this approach is needed as a way to maintain urban assets that significantly contribute to the establishment of values and quality parts of the city. Heritage planning is also the act of communicating and remembering the past for the present and the future in the public domain. This paper aims to formulate a conceptual heritage planning of designating heritage sites that challenges the traditional notion of heritage which considers age as a key element in heritage, the privileges monumentality and grand scale, with scientific/aesthetic expert judgment as a requirement of heritage designations. The limited idea of heritage based on exclusive values as something ancient, grand-scale, historical, and with other exclusive values has excluded many places as heritage in communities emerging from disasters. Debates within the critical heritage studies movement argue that heritage is a cultural product linked to activities of remembering and is an act of communication. The dominant hypothesis is that heritage values cannot remain to exist if the physical or material aspects of sites are destroyed and this hypothesis feels flawed. This paper asks us to acknowledge the

Final report on the radiological surveys of designated DX firing sites at Los Alamos National Laboratory

International Nuclear Information System (INIS)

1996-01-01

CHEMRAD was contracted by Los Alamos National Laboratory to perform USRADS reg-sign (UltraSonic Ranging And Data System) radiation scanning surveys at designated DX Sites at the Los Alamos National Laboratory. The primary purpose of these scanning surveys was to identify the presence of Depleted Uranium (D-38) resulting from activities at the DX Firing Sites. This effort was conducted to update the most recent surveys of these areas. This current effort was initiated with site orientation on August 12, 1996. Surveys were completed in the field on September 4, 1996. This Executive Summary briefly presents the major findings of this work. The detail survey results are presented in the balance of this report and are organized by Technical Area and Site number in section 2. This organization is not in chronological order. USRADS and the related survey methods are described in section 3. Quality Control issues are addressed in section 4. Surveys were conducted with an array of radiation detectors either mounted on a backpack frame for man-carried use (Manual mode) or on a tricycle cart (RadCart mode). The array included radiation detectors for gamma and beta surface near surface contamination as well as dose rate at 1 meter above grade. The radiation detectors were interfaced directly to an USRADS 2100 Data Pack

Technical basis for the ITER-FEAT outline design. Progress in resolving open design issues from the outline design report

International Nuclear Information System (INIS)

2000-01-01

In this publication the technical basis for the ITER-FEAT outline design is presented. It comprises the Plant Design Specifications, the Safety Principles and Environmental Criteria, the Site Requirements and Site Design Assumptions. The outline of the key features of the ITER-FEAT design includes main physical parameters and assessment, design overview and preliminary safety assessment, cost and schedule

Implementing ‘Site BIM’

DEFF Research Database (Denmark)

Davies, Richard; Harty, Chris

2013-01-01

Numerous Building Information Modelling (BIM) tools are well established and potentially beneficial in certain uses. However, issues of adoption and implementation persist, particularly for on-site use of BIM tools in the construction phase. We describe an empirical case-study of the implementation...... of an innovative ‘Site BIM’ system on a major hospital construction project. The main contractor on the project developed BIM-enabled tools to allow site workers using mobile tablet personal computers to access design information and to capture work quality and progress data on-site. Accounts show that ‘Site BIM...

"A Virtual Canvas"—Designing a Blog Site to Research Young Muslims' Friendships & Identities

Directory of Open Access Journals (Sweden)

Orla McGarry

2012-11-01

Full Text Available This article is based on research among a group of Muslim youth living in the west of Ireland as part of a study on "social belonging" and identity. One part of the research involved designing a youth centered, participatory research method, in the form of a blog site, to investigate what young people say and do when they are asked to talk about themselves and their relationships, with minimal researcher involvement. Participants were presented with a "blank virtual canvas" where they determined what became discussed. Twenty-two teenaged Muslims—comprising close friends as well as fellow students of the same school and living in the same West of Ireland town—contributed to a time limited, closed blog site over a four month period. The blog site offers interesting snippets of Muslim identification, and how they choose to present themselves to others. In the process of contributing to this exercise, we can also observe subtle means through which inclusion and exclusion co-exist online, refracting young people's offline worlds. The blog affords an opportunity to consciously "do" friendship by presenting to each other images, symbols and statements of friendship that invoke both cohesion and closure. The research unravels certain gendered patterns in online performances. In demonstrating this evidence, we argue that the study of online interactions of youth can provide an alternative window in exploring relationships, identification and social positioning. URN: http://nbn-resolving.de/urn:nbn:de:0114-fqs130115

Final work plan: Expedited Site Characterization of the IES Industries, Inc., Site at Marshalltown, Iowa. Ames Expedited Site Characterization Project, Version 1.0

Energy Technology Data Exchange (ETDEWEB)

1994-04-04

The overall goal of the Ames Laboratory Expedited Site Characterization (ESC) project is to evaluate and promote both innovative and state-of-the-practice site characterization and/or monitoring technologies. This will be accomplished by fielding both types of technologies together in the context of an expedited site characterization. The first site will be at a former manufactured gas plant (FMGP) in Marshalltown, Iowa. The project will field three areas of technology: geophysical, analytical, and data fusion. Geophysical technologies are designed to understand the subsurface geology to help predict fate and transport of the target contaminants. Analytical technologies/methods are designed to detect and quantify the target contaminants. Data fusion technology consists of software systems designed to rapidly integrate or fuse all site information into a conceptual site model that then becomes the decision making tool for the site team to plan subsequent sampling activity. Not all of the contaminants present can be located at the action level. Polynuclear aromatic hydrocarbons (PAHs) are the signature organics associated with the coal tar activities that took place at the site. As a result, PAHs were selected as the target compounds. Screening analytical instruments and nonintrusive geophysical techniques will be fielded to qualitatively map the spatial contaminant distribution. Soil gas surveys, immunoassay testing (IMA), innovative optical techniques, and passive organic sorbent sensors will be deployed along with the geophysical methods. Gas chromatography/mass spectrometry (GC/MS) instruments and a cone penetrometer system equipped with a laser-induced fluorescence (LIF) probe will quantitatively map the action level edges of the PAH plume(s). Samples will be taken both by the cone penetrometer test system (CPT) and the Geoprobe {reg_sign} sampler system.

Feedback from performance assessment to site characterisation. The SITE-94 example

International Nuclear Information System (INIS)

Dverstorp, B.; Geier, J.

1999-01-01

Interaction and information exchange between site characterisation and performance assessment are key features of any successful radioactive waste management programme. Some examples are presented of the types of feedback that can be offered from performance assessment to site characterisation, based on SKI's most recent performance assessment project, SITE-94. SITE-94 in Sweden was an assessment of a hypothetical repository for spent nuclear fuel, based on real data gathered in the surface-based investigation of the Aespoe Hard Rock Laboratory site. Examples of feedback are given concerning quality control of data and site investigation procedures, identification of key parameters for the performance assessment, use of models for planning and evaluation of a site investigation, data sampling strategies, and guidance on future priorities for further development of site investigation methods. Because site characterisation serves multiple purposes, including provision of data for repository design and construction, it must account for and compromise among requirements from several lines of analyses in the performance assessment. (author)

Energy conserving site design case study: Shenandoah, Georgia. Final report

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

The case study examines the means by which energy conservation can be achieved at an aggregate community level by using proper planning and analytical techniques for a new town, Shenandoah, Georgia, located twenty-five miles southwest of Atlanta's Hartsfield International Airport. A potentially implementable energy conservation community plan is achieved by a study team examining the land use options, siting characteristics of each building type, alternate infrastructure plans, possible decentralized energy options, and central utility schemes to determine how community energy conservation can be achieved by use of pre-construction planning. The concept for the development of mixed land uses as a passively sited, energy conserving community is based on a plan (Level 1 Plan) that uses the natural site characteristics, maximizes on passive energy siting requirement, and allows flexibility for the changing needs of the developers. The Level 2 Plan is identical with Level 1 plan plus a series of decentraized systems that have been added to the residential units: the single-family detached, the apartments, and the townhouses. Level 3 Plan is similar to the Level 1 Plan except that higher density dwellings have been moved to areas adjacent to central site. The total energy savings for each plan relative to the conventional plan are indicated. (MCW)

Site-specific Seismic Hazard Assessment to Establish Elastic Design Properties for Oman Museum-Across Ages, Manah, Sultante of Oman

Science.gov (United States)

El Hussain, I. W.

2017-12-01

The current study provides a site specific deterministic seismic hazard assessment (DSHA) at the selected site for establishing the Oman Museum-Across Ages at Manah area, as a part of a comprehensive geotechnical and seismological plan to design the facilities accordingly. The DSHA first defines the seismic sources that might influence the site and assesses the maximum possible earthquake magnitude for each of them. By assuming each of these maximum earthquakes to occur at a location placing them at the closest distances to the site, the ground motion is predicted utilizing empirical ground motion prediction equations. The local site effects are performed by determining the fundamental frequency of the soft soil using HVSR technique and by estimating amplification spectra using the soil characteristics (mainly shear-wave velocity). Shear-wave velocity has been evaluated using the MASW technique. The maximum amplification value of 2.1 at spectral period 0.06 sec is observed at the ground surface, while the largest amplification value at the top of the conglomerate layer (at 5m depth) is 1.6 for a spectral period of 0.04 Sec. The maximum median 5% damped peak ground acceleration is found to be 0.263g at a spectral period of 0.1 sec. Keywords: DSHA; Site Effects; HVSR; MASW; PGA; Spectral Period

ICRPfinder: a fast pattern design algorithm for coding sequences and its application in finding potential restriction enzyme recognition sites

Directory of Open Access Journals (Sweden)

Stafford Phillip

2009-09-01

Full Text Available Abstract Background Restriction enzymes can produce easily definable segments from DNA sequences by using a variety of cut patterns. There are, however, no software tools that can aid in gene building -- that is, modifying wild-type DNA sequences to express the same wild-type amino acid sequences but with enhanced codons, specific cut sites, unique post-translational modifications, and other engineered-in components for recombinant applications. A fast DNA pattern design algorithm, ICRPfinder, is provided in this paper and applied to find or create potential recognition sites in target coding sequences. Results ICRPfinder is applied to find or create restriction enzyme recognition sites by introducing silent mutations. The algorithm is shown capable of mapping existing cut-sites but importantly it also can generate specified new unique cut-sites within a specified region that are guaranteed not to be present elsewhere in the DNA sequence. Conclusion ICRPfinder is a powerful tool for finding or creating specific DNA patterns in a given target coding sequence. ICRPfinder finds or creates patterns, which can include restriction enzyme recognition sites, without changing the translated protein sequence. ICRPfinder is a browser-based JavaScript application and it can run on any platform, in on-line or off-line mode.

Assessment of candidate sites for disposal of treated effluents at the Hanford Site, Washington

International Nuclear Information System (INIS)

Davis, J.D.

1992-01-01

A rigidly defined evaluation process was used to recommend a preferred location to dispose of treated effluents from facilities in the 200 Areas of the US Department of Energy's Hanford Site in Washington State. First, siting constraints were defined based on functional design considerations and siting guidelines. Then, criteria for selecting a preferred site from among several candidates were identified and their relative importance defined. Finally, the weighted criteria were applied and a site was selected for detailed characterization by subsurface investigations

Design principle of TVO's final repository and preliminary adaptation to site specific conditions

International Nuclear Information System (INIS)

Salo, J-P.; Reikkola, R.

1995-01-01

Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs

Cost estimate of the Yucca Mountain repository based on the site characterization plan conceptual design: Nevada Nuclear Waste Storage Investigations Project

International Nuclear Information System (INIS)

Gruer, E.R.; Fowler, M.E.; Rocha, G.A.

1987-06-01

This report of the life-cycle costs of a mined repository in tuff is based on the site characterization conceptual design and contains estimates of two methods of waste emplacement - vertical and horizontal. The life cycle of the repository progresses from design and construction to emplacement operations that last 25 years. When emplacement has ended, a caretaker period begins and continues until 50 years from emplacement of the first waste. The life of the repository concludes with closure and decommissioning, which includes backfilling and sealing the repository, decontaminating and razing the surface facilities, restoring the land to as near its original condition as possible, and marking the site. The estimates, developed for each phase of the life cycle of the repository, are based on January 1986 constant (unescalated) dollars and include an allowance for contingency. This report mainly comprises explanations of design and operating assumptions, estimating methods, exclusions, definition of cost accounts, calculating procedures, data sources, staffing and other qualifying remarks. Cost estimates are approximations of value and should not be construed as exact. The cost and staffing detail provided in this estimate is commensurate with the detail in the conceptual design

Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, vertical emplacement mode: Volume 1

International Nuclear Information System (INIS)

1987-12-01

This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs

Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, vertical emplacement mode: Volume 1

Energy Technology Data Exchange (ETDEWEB)

1987-12-01

This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packing, and other surface facility operations are described. Operations in the shafts underground are described, including waste hoisting, transfer, and vertical emplacement. This report specifically addresses the vertical emplacement mode, the reference design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs.

Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, horizontal emplacment mode: Volume 1

International Nuclear Information System (INIS)

1987-12-01

This Conceptual Design Report describes the conceptual design of a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. Waste receipt, processing, packaging, and other surface facility operations are described. Operations in the shafts and underground are described, including waste hoisting, transfer, and horizontal emplacement. This report specifically addresses the horizontal emplacement mode, the passive alternate design for the repository. Waste retrieval capability is described. The report includes a description of the layout of the surface, shafts, and underground. Major equipment items are identified. The report includes plans for decommissioning and sealing of the facility. The report discusses how the repository will satisfy performance objectives. Chapters are included on basis for design, design analyses, and data requirements for completion of future design efforts. 105 figs., 52 tabs

Natura2000 : information and communication on the designation and management of Natura2000 sites : main report 3: towards integrated management

NARCIS (Netherlands)

Kruk, R.W.; Blust, de G.; Apeldoorn, van R.C.; Bouwma, I.M.; Sier, A.R.J.

2010-01-01

Natura2000 : information and communication on the designation and management of Natura2000 sites. For all member states information will be collected describing the necessary management approaches, their legal framework, public consultation procedures as well as timing, structure and content of

Postclosure performance assessment of the SCP [Site Characterization Plan] conceptual design for horizontal emplacement: Revision 1

International Nuclear Information System (INIS)

1987-08-01

This report is a preliminary postclosure performance assessment of the repository design specified in the Site Characterization Plan Conceptual Design Report (SCP-CDR) for horizontal emplacement of high-level nuclear waste. At the time that these analyses were done, horizontal emplacement was the preferred orientation for the waste packages but vertical emplacement is now the reference design. This assessment consists of (1) a review of the regulatory requirements and strategy to demonstrate compliance with these requirements, (2) an analysis of the performance of the total repository system, (3) an analysis of the thermomechanical behavior of the repository, (4) an analysis of brine mobility in the repository, (5) an analysis of the waste package performance, (6) an analysis of the performance of seals, and (7) comments on the sensitivity of the various performance measures to uncertainties in the data and models. These are preliminary analyses and, in most cases, involve bounding calculations of the repository behavior. They have several purposes including (1) assessing how well this conceptual design ''measures up'' against requirements, (2) gaining experience in implementing the performance assessment strategy and tools and thereby learning where improvements are needed, (3) helping to identify needed data, and (4) helping to indicate required design modifications. 26 refs., 40 figs., 20 tabs

SU-E-T-760: Tolerance Design for Site-Specific Range in Proton Patient QA Process Using the Six Sigma Model

International Nuclear Information System (INIS)

Lah, J; Shin, D; Kim, G

2015-01-01

Purpose: To show how tolerance design and tolerancing approaches can be used to predict and improve the site-specific range in patient QA process in implementing the Six Sigma. Methods: In this study, patient QA plans were selected according to 6 site-treatment groups: head &neck (94 cases), spine (76 cases), lung (89 cases), liver (53 cases), pancreas (55 cases), and prostate (121 cases), treated between 2007 and 2013. We evaluated a model of the Six Sigma that determines allowable deviations in design parameters and process variables in patient-specific QA, where possible, tolerance may be loosened, then customized if it necessary to meet the functional requirements. A Six Sigma problem-solving methodology is known as DMAIC phases, which are used stand for: Define a problem or improvement opportunity, Measure process performance, Analyze the process to determine the root causes of poor performance, Improve the process by fixing root causes, Control the improved process to hold the gains. Results: The process capability for patient-specific range QA is 0.65 with only ±1 mm of tolerance criteria. Our results suggested the tolerance level of ±2–3 mm for prostate and liver cases and ±5 mm for lung cases. We found that customized tolerance between calculated and measured range reduce that patient QA plan failure and almost all sites had failure rates less than 1%. The average QA time also improved from 2 hr to less than 1 hr for all including planning and converting process, depth-dose measurement and evaluation. Conclusion: The objective of tolerance design is to achieve optimization beyond that obtained through QA process improvement and statistical analysis function detailing to implement a Six Sigma capable design

SU-E-T-760: Tolerance Design for Site-Specific Range in Proton Patient QA Process Using the Six Sigma Model

Energy Technology Data Exchange (ETDEWEB)

Lah, J [Myongji Hospital, Goyang, Gyeonggi-do (Korea, Republic of); Shin, D [National Cancer Center, Goyang-si, Gyeonggi-do (Korea, Republic of); Kim, G [University of California, San Diego, La Jolla, CA (United States)

2015-06-15

Purpose: To show how tolerance design and tolerancing approaches can be used to predict and improve the site-specific range in patient QA process in implementing the Six Sigma. Methods: In this study, patient QA plans were selected according to 6 site-treatment groups: head &neck (94 cases), spine (76 cases), lung (89 cases), liver (53 cases), pancreas (55 cases), and prostate (121 cases), treated between 2007 and 2013. We evaluated a model of the Six Sigma that determines allowable deviations in design parameters and process variables in patient-specific QA, where possible, tolerance may be loosened, then customized if it necessary to meet the functional requirements. A Six Sigma problem-solving methodology is known as DMAIC phases, which are used stand for: Define a problem or improvement opportunity, Measure process performance, Analyze the process to determine the root causes of poor performance, Improve the process by fixing root causes, Control the improved process to hold the gains. Results: The process capability for patient-specific range QA is 0.65 with only ±1 mm of tolerance criteria. Our results suggested the tolerance level of ±2–3 mm for prostate and liver cases and ±5 mm for lung cases. We found that customized tolerance between calculated and measured range reduce that patient QA plan failure and almost all sites had failure rates less than 1%. The average QA time also improved from 2 hr to less than 1 hr for all including planning and converting process, depth-dose measurement and evaluation. Conclusion: The objective of tolerance design is to achieve optimization beyond that obtained through QA process improvement and statistical analysis function detailing to implement a Six Sigma capable design.

Rational design of a conformation-switchable Ca2+- and Tb3+-binding protein without the use of multiple coupled metal-binding sites.

Science.gov (United States)

Li, Shunyi; Yang, Wei; Maniccia, Anna W; Barrow, Doyle; Tjong, Harianto; Zhou, Huan-Xiang; Yang, Jenny J

2008-10-01

Ca2+, as a messenger of signal transduction, regulates numerous target molecules via Ca2+-induced conformational changes. Investigation into the determinants for Ca2+-induced conformational change is often impeded by cooperativity between multiple metal-binding sites or protein oligomerization in naturally occurring proteins. To dissect the relative contributions of key determinants for Ca2+-dependent conformational changes, we report the design of a single-site Ca2+-binding protein (CD2.trigger) created by altering charged residues at an electrostatically sensitive location on the surface of the host protein rat Cluster of Differentiation 2 (CD2).CD2.trigger binds to Tb3+ and Ca2+ with dissociation constants of 0.3 +/- 0.1 and 90 +/- 25 microM, respectively. This protein is largely unfolded in the absence of metal ions at physiological pH, but Tb3+ or Ca2+ binding results in folding of the native-like conformation. Neutralization of the charged coordination residues, either by mutation or protonation, similarly induces folding of the protein. The control of a major conformational change by a single Ca2+ ion, achieved on a protein designed without reliance on sequence similarity to known Ca2+-dependent proteins and coupled metal-binding sites, represents an important step in the design of trigger proteins.

Energy-conserving site-design case study, Radisson, New York. Final report

Energy Technology Data Exchange (ETDEWEB)

1979-12-01

Radisson is a 2,950-acre new community currently being developed by the New York State Urban Development Corporation and located in central New York, 12 miles north-west of Syracuse. Case-study sites selected for this project are a 95-acre residential site and the 51-acre Town Center of the new community. Development on the Residential Site is a low-density (2.8 dwelling units/acre) mixture of single-family, townhouse and multi-family units. Development on the Town Center site is a mixture of small-scale commercial use (144,000 sq. ft.) and 330+ multi-family dwelling units. Energy-conserving plans developed for both sites have focused on passive measures to reduce energy use for space heating. Utility-system options have been identified for both sites, but require further study as to feasibility and cost. This report summarizes energy savings and cost differentials due to passive measures incorporated in both the residential and Town Center Plans. The future implementation schedule, also discussed, summarizes the procedures an schedule required for implementation of the passive measures, as well as further study required for the development of utility-system options. 4 tables.

Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2006-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area

Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2006-06-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area.

Development of a design package for a viscous barrier at the Savannah River Site

International Nuclear Information System (INIS)

Moridis, G.J.; James, A.; Oldenburg, C.

1996-10-01

This paper describes elements of a design for a pilot-scale field demonstration of a new subsurface containment technology for waste isolation developed at the Lawrence Berkeley National Laboratory (LBNL), which uses a new generation of barrier liquids for permeation grouting. The demonstration site was Retention Basin 281-3H, a shallow catchment basin at the Savannah River Site (SRS), originally built to control contaminated runoff for the H Reactor, and which has been contaminated mainly by radionuclides. The LBNL viscous barrier technology employs barrier liquids which, when injected into the subsurface, produce chemically benign nearly impermeable barriers through a very large increase in viscosity. The initially low-viscosity liquids are emplaced through multiple injection points in the subsurface and the intersecting plumes merge and completely surround the contaminant source and/or plume. Once in place, they gel or cure to form a nearly impermeable barrier. The barrier liquid to be used in this application is Colloidal Silica (CS), an aqueous suspension of silica microspheres in a stabilizing electrolyte. It has excellent durability characteristics, poses no health hazard, is practically unaffected by filtration, and is chemically and biologically benign

Site study plan for cultural resources, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-06-01

The Cultural Resources Site Study Plan describes a field program to identify and evaluate the archaeological, historical, and Native American Indian resources of the site on local and regional perspectives; monitor and manage discovered cultural resources; and establish a worker education program. The archaeological field program consists of three pedestrian surveys: Survey 1 includes two EDBH seismic survey lines and the area within the exploratory shaft facility (ESF); Survey 2 includes the remainder of the site plus a 1/4 to 3/4-mi border area; and Survey 3 includes an assortment of offsite areas. The historical studies will identify and evaluate known and discovered historical sites and structures and the Native American Indian will identify and evaluate cultural and religious concerns expressed by Indian tribal groups. Prehistoric and historic sites will be evaluated to determine if they meet eligibility criteria for listing on the National Register of Historic Places. This site study plan describes the need for each study; its design and design rationale; analysis, management, and use of data; schedule of field activities; organization of field personnel and sample management; and quality assurance requirements. The cultural resource studies will provide data for satisfying the Programmatic Agreement, engineering design needs, and SRP requirements for permits and approvals, and for minimizing effects to any cultural properties discovered during site characterization. 75 refs., 10 figs., 2 tabs

Design Considerations for Multilingual Web Sites

Directory of Open Access Journals (Sweden)

Joan Starr

2005-09-01

Full Text Available The most powerful marketing, service, and information-distribution tool a library has today is its Web site, but providing Web content in many languages is complex. Before allocating scarce technical and financial resources, it is valuable to learn about writing systems, types of writing, how computers render and represent writing systems, and to study potential problem areas and their possible solutions. The accepted Web standard for presenting languages is Unicode and a full understanding of its history and the coding tools it provides is essential to making appropriate decisions for specific multilingual and internationalization projects. Actual coding examples, as well as a sampling of existing multilingual library services, also serve to illuminate the path of implementation.

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado

International Nuclear Information System (INIS)

1992-10-01

The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (40 CFR 192). The US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined this assessment shall include information on hydrogeologic site characterization. This document contains appendices to Attachment 3, Groundwater Hydrology Report included are calculations

Readability of Online Patient Educational Resources Found on NCI-Designated Cancer Center Web Sites.

Science.gov (United States)

Rosenberg, Stephen A; Francis, David; Hullett, Craig R; Morris, Zachary S; Fisher, Michael M; Brower, Jeffrey V; Bradley, Kristin A; Anderson, Bethany M; Bassetti, Michael F; Kimple, Randall J

2016-06-01

The NIH and Department of Health & Human Services recommend online patient information (OPI) be written at a sixth grade level. We used a panel of readability analyses to assess OPI from NCI-Designated Cancer Center (NCIDCC) Web sites. Cancer.gov was used to identify 68 NCIDCC Web sites from which we collected both general OPI and OPI specific to breast, prostate, lung, and colon cancers. This text was analyzed by 10 commonly used readability tests: the New Dale-Chall Readability Formula, Flesch Reading Ease scale, Flesch-Kinaid Grade Level, FORCAST scale, Fry Readability Graph, Simple Measure of Gobbledygook test, Gunning Frequency of Gobbledygook index, New Fog Count, Raygor Readability Estimate Graph, and Coleman-Liau Index. We tested the hypothesis that the readability of NCIDCC OPI was written at the sixth grade level. Secondary analyses were performed to compare readability of OPI between comprehensive and noncomprehensive centers, by region, and to OPI produced by the American Cancer Society (ACS). A mean of 30,507 words from 40 comprehensive and 18 noncomprehensive NCIDCCs was analyzed (7 nonclinical and 3 without appropriate OPI were excluded). Using a composite grade level score, the mean readability score of 12.46 (ie, college level: 95% CI, 12.13-12.79) was significantly greater than the target grade level of 6 (middle-school: Preadability metrics (P<.05). ACS OPI provides easier language, at the seventh to ninth grade level, across all tests (P<.01). OPI from NCIDCC Web sites is more complex than recommended for the average patient. Copyright © 2016 by the National Comprehensive Cancer Network.

Geochemical investigation of UMTRAP designated site at Canonsburg, Pennsylvania

International Nuclear Information System (INIS)

Markos, G.; Bush, K.J.; Freeman, T.

1981-05-01

UMTRAP is an acronym for Uranium Mill Tailings Remedial Action Project. The Canonsburg, Pennsylvania site was utilized from 1911 to 1922 and from 1930 to 1942, first to remove radium from sedimentary uranium ore, and later to remove uranium from ore as well as process various materials, ceasing operations in 1957. Of the three areas, Area A is the former mill site and is occupied in part by present industrial activities. Area B is comprised of mill residues mixed with sediment dredged from Chartiers Creek, a disturbed terrace along Chartiers Creek, and a ditch on the north side. The ditch contains water with the highest concentrations of contaminants measured in the Canonsburg site. It is believed that unprocessed ore is deposited here and effluent from leaks in a sewer line across the north edge of Areas A and B carry contaminants from heavily contaminated drains in the buildings of Area A. Area C contains the former liquid disposal lagoon, and the central part of the area is highly contaminated to a depth of about 3 meters. Area C contains the most concentrated waste material with maximum levels (except for the ditch on the north side of Area B) of all the contaminants distributed throughout the area. Contamination outside the site is limited. The presence of contaminants in the ditches, in the soils on the river bank, and below the tailings pile is not attributed to migration processes, but rather to the presence of ore materials and concentrated wastes mechanically dispersed throughout the area

Case study of siting technology for underground nuclear power plant

International Nuclear Information System (INIS)

Hibino, Satoshi; Komada, Hiroya; Honsho, Shizumitsu; Fujiwara, Yoshikazu; Motojima, Mutsumi; Nakagawa, Kameichiro; Nosaki, Takashi

1991-01-01

Underground siting method is one of new feasible siting methods for nuclear power plants. This report presents the results on case studies on underground siting. Two sites of a steeply inclined and plateau like configurations were selected. 'Tunnel type cavern; all underground siting' method was applied for the steeply inclined configuration, and 'shaft type semi-cavern; partial underground siting' method was applied for the plateau like configuration. The following designs were carried out for these two sites as case studies; (1) conceptual designs, (2) geological surveys and rock mechanics tests, (3) stability analysis during cavern excavations, (4) seismic stability analysis of caverns during earthquake, (5) reinforcement designs for caverns, (6) drainage designs. The case studies showed that these two cases were fully feasible, and comparison between two cases revealed that the 'shaft type semi-cavern; partial underground siting' method was more suitable for Japanese islands. As a first step of underground siting, therefore, the authors recommend to construct a nuclear power plant by this method. (author)

Japanese site for ITER: Rokkasho

International Nuclear Information System (INIS)

Kishimoto, Hiroshi

2003-01-01

This paper describes the status of Japanese efforts for hosting ITER in Japan. In May 2002, Japanese Government decided to propose an ITER site, Rokkasho in Aomori Prefecture, a Northern part of the main island, based on the comprehensive/intensive assessments by the Site Selection Committee established by Japanese Government. ITER is designed basically with a potential flexibility beyond the detailed technical objectives to have more clear scope for developing technical key elements in a future power plant. Various flexibilities in the construction, operation and decommissioning of ITER are totally assessed. Consequently the Japanese site has been chosen and it satisfies sufficiently not only the Site Requirements and the Site Design Assumptions but also the further extension and flexibilities. In particular the potential for more flexible construction schedule and operations is technically described as well as the fulfillment of the site requirements and its assumptions as the minimum requirements in this paper. The socio-cultural environment is also described briefly because of a key aspect for the scientists and engineers who will participate in the project

Development of the radiological protection focus in the site, design and construction of the nuclear power plant in Cuba

International Nuclear Information System (INIS)

Rodriguez R, J.M.

1996-01-01

The first nuclear station in Cuba NPP Juragua, at present in analysis for starting again the construction, under a multinational economic association, had had as main architect/engineer organization the Design Institute for Nuclear Power Stations of St. Petersburg (former LIAEP). Active participation of Cuban radiation protection specialist of Energoproyecto in the Juragua Project began at the beginning of the site selection works and continued in the design and construction stages up till now, and simultaneously our specialists have been acting as a counterpart of soviet designers, responsible for the general design of the station. Furthermore, some additional works in compliance with the latest safety requirements and the best international practices, which are described, as well as ongoing and planned work were performed. (author). 11 refs., 3 figs

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-01-01

Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requirements of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs.

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

International Nuclear Information System (INIS)

1988-01-01

Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requiremenrs of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs

Meteorology in site operations

International Nuclear Information System (INIS)

Anon.

1986-01-01

During the site selection and design phases of a plant, meteorological assistance must be based on past records, usually accumulated at stations not actually on the site. These preliminary atadvices will be averages and extremes that might be expected. After a location has been chosen and work has begun, current and forecast weather conditions become of immediate concern. On-site meteorological observations and forecasts have many applications to the operating program of an atomic energy site. Requirements may range from observations of the daily minimum temperatures to forecasts of radiation dosages from airborne clouds

Evaluation of a multi-site program designed to strengthen relational bonds for siblings separated by foster care.

Science.gov (United States)

Waid, Jeffrey; Wojciak, Armeda Stevenson

2017-10-01

Sibling relationships in foster care settings have received increased attention in recent years. Despite growing evidence regarding the protective potential of sibling relationships for youth in care, some sibling groups continue to experience foster care related separation, and few programs exist to address the needs of these youth. This study describes and evaluates Camp To Belong, a multi-site program designed to provide short-term reunification to separated sibling groups through a week-long summer camp experience. Using a pre-test post-test survey design, this paper examines changes in youth ratings of sibling conflict and sibling support across camps located in six geographically distinct regions of the United States. The effects of youth age, number of prior camp exposures, and camp location were tested using multilevel modeling procedures. Findings suggest that participation in Camp To Belong may reduce sibling conflict, and improvements in sibling support are noted for youth who have had prior exposure to the camp's programming. Camp-level variance in the sibling support outcome highlight the complex nature of relationships for siblings separated by foster care, and suggest the need for additional research. Lessons learned from this multi-site evaluation and future directions are discussed. Copyright © 2017 Elsevier Ltd. All rights reserved.

Bedrock hydrogeology Forsmark. Site descriptive modelling, SDM-Site Forsmark

Energy Technology Data Exchange (ETDEWEB)

Follin, Sven (SF GeoLogic AB, Taeby (Sweden))

2008-12-15

The Swedish Nuclear Fuel and Waste Management Company (SKB) has conducted site investigations at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a final repository for spent nuclear fuel according to the KBS-3 concept. Site characterisation should provide all data required for an integrated evaluation of the suitability of the investigated site and an important component in the characterisation work is the development of a hydrogeological model. The hydrogeological model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It also provides input to the safety assessment. Another important use of the hydrogeological model is in the environmental impact assessment. This report presents the understanding of the hydrogeological conditions of the bedrock at Forsmark reached following the completion of the surface-based investigations and provides a summary of the bedrock hydrogeological model and the underlying data supporting its development. It constitutes the main reference on bedrock hydrogeology for the site descriptive model concluding the surface-based investigations at Forsmark, SDM-site, and is intended to describe the hydraulic properties and hydrogeological conditions of the bedrock at the site and to give the information essential for demonstrating understanding

Cold shock to aquatic organisms: guidance for power-plant siting, design, and operation

International Nuclear Information System (INIS)

Coutant, C.C.

1977-01-01

Problems of cold-shock damages to aquatic organisms have arisen at some condenser cooling-water discharges of thermal power stations when the warm-water releases have suddenly terminated. The basis for such damage lies in the exposure of resident organisms to a rapid decrease in temperature and a sustained exposure to low temperature that induces abnormal behavioral or physiological performance and often leads to death. Although some spectacular fish kills from cold shock have occurred, the present knowledge of the hydraulic and biological processes involved can provide guidance for the siting, design, and operation of power-plant cooling systems to minimize the likelihood of significant cold-shock effects. Preventing cold-shock damages is one consideration in minimizing overall environmental impacts of power-plant cooling and in balancing plant costs with environmental benefits

Investigation of layered covers designed to limit infiltration at waste disposal sites

International Nuclear Information System (INIS)

Johnson, T.M.; Herzog, B.L.; Cartwright, K.; Larson, T.H.

1983-01-01

Layered soils of highly contrasting texture have been shown to act as a barrier to infiltration because of differences in unsaturated hydraulic properties. Water infiltrating into a fine-grained soil overlying an unsaturated gravel will not enter the gravel until the overlying material is nearly saturated. As a result of what is commonly called the wick effect, moisture will flow laterally through the fine-grained soil above the gravel layer. Layered covers of compacted soil materials utilizing this phenomenon have been proposed to limit infiltration at waste disposal sites. A study funded by the US Nuclear Regulatory Commission is underway to evaluate the potential use of layered trench covers to minimize infiltration at low-level radioactive waste disposal sites. Moisture movement through layered covers consisting of compacted fine-grained soils and sand or gravel was modeled, using a one-dimensional finite-difference model to compare with laboratory column experiments and a two-dimensional finite-element model for field-scale simulations. Soil-moisture characteristic data were obtained from laboratory experiments and the hydraulic conductivity was calculated as a function of capillary pressure. The numerical simulations indicate that layered covers using various combinations of compacted fine-grained soils and coarse-grained material are able to substantially reduce infiltration. Laboratory column experiments using a dual-gamma ray attenuation system to measure moisture content and density simultaneously have been used to observe the behavior of layered soils and to select materials for field testing. Currently underway are field-scale studies of alternative cover designs selected on the basis of two-dimensional modeling

Early Site Permit Demonstration Program: Plant parameters envelope report

International Nuclear Information System (INIS)

1993-03-01

The Early Site Permit (ESP) Demonstration Program is the nuclear industry's initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1994-03-01

Attachment 3 Groundwater Hydrology Report describes the hydrogeology, water quality, and water resources at the processing site and Dry Flats disposal site. The Hydrological Services calculations contained in Appendix A of Attachment 3, are presented in a separate report. Attachment 4 Water Resources Protection Strategy describes how the remedial action will be in compliance with the proposed EPA groundwater standards

Proposal for the award of a contract for provision of mechanical design and draughting services off the CERN site

CERN Document Server

2004-01-01

This document concerns the award of a contract for the provision of mechanical design and draughting services off the CERN site. Following a market survey carried out among 62 firms in fifteen Member States, a call for tenders (IT-3213/EST) was sent on 19 January 2004 to eight firms, in seven Member States. By the closing date, CERN had received eight tenders from eight firms in seven Member States. The Finance Committee is invited to agree to the negotiation of a contract with ACROTECNA (FR), the lowest bidder, for the provision of mechanical design and draughting services off the CERN site for an amount of 489 373 euros (771 882 Swiss francs) for an initial period of three years starting on 1 July 2004, subject to revision for inflation from 1 July 2007. The rate of exchange used is that stipulated in the tender. The contract will include options for two one-year extensions beyond the initial three-year period. The firm has indicated the following distribution by country of the contract value covered by thi...

Plans for characterization of salt sites

International Nuclear Information System (INIS)

Heim, G.E.; Matthews, S.C.; Kircher, J.F.; Kennedy, R.K.

1983-01-01

This basic salt site characterization program has been designed to provide the data required to support the design, performance assessment, and licensing of each of the principal project elements: the repository, the shafts, and the surface facilities. The work has been sequenced to meet the design and licensing schedule. It is anticipated that additional characterization activities will be performed to address site-specific considerations and to provide additional information to address questions which arise during the evaluation of characterization data. 3 figures, 3 tables

Near Regional and Site Investigations of the Temelin NPP Site

International Nuclear Information System (INIS)

Prachar, Ivan; Vacek, Jiri; Heralecky, Pavel

2011-01-01

The Temelin NPP is worldwide through heated discussion with nuclear energetic opposition. In addition this discussion goes beyond a border of the Czech Republic. On the other side, results of several international supervisions shown that Temelin NPP is fully comparable with the safest nuclear power plants in the world regarding its technical design and safety functions. This presentation deals with the near regional and site investigations of the Temelin NPP Site. It must be noted that although the Temelin site is situated in the area with low seismicity, item of seismicity is a basic argument against Temelin NPP and therefore a detail seismic hazard assessment was performed

Status report: Fernald site remediation

International Nuclear Information System (INIS)

Craig, J.R. Jr.; Saric, J.A.; Schneider, T.; Yates, M.K.

1995-01-01

The Fernald site is rapidly transitioning from a Remedial Investigation/ Feasibility Study (RI/FS) site to one where design and construction of the remedies dominates. Fernald is one of the first sites in the Department of Energy (DOE) complex to accomplish this task and real physical progress is being made in moving the five operable units through the CERCLA process. Two of the required Records of Decision (ROD) are in hand and all five operable units will have received their RODs (IROD for OU3) by the end of 1995. Pre-design investigations, design work or construction are now in progress on the operable units. The lessons learned from the work done to date include implementing innovations in the RI and FS process as well as effective use of Removal Actions to begin the actual site remediation. Also, forging close working relationships with the Federal and State Regulators, citizens action groups and the Fernald Citizens Task Force has helped move the program forward. The Fernald successes have been achieved by close coordination and cooperation among all groups working on the projects and by application of innovative technologies within the decision making process

Visualization of Safety Assessment Result Using GIS in SITES

International Nuclear Information System (INIS)

Yun, Bong-Yo; Park, Joo Wan; Park, Se-Moon; Kim, Chang-Lak

2006-01-01

Site Information and Total Environmental database management System (SITES) is an integrated program for overall data analysis, environmental monitoring, and safety analysis that are produced from the site investigation and environmental assessment of the relevant nuclear facility. SITES is composed of three main modules such as Site Environment Characterization database for Unified and Reliable Evaluation system (SECURE), Safety Assessment INTegration system (SAINT) and Site Useful Data Analysis and ALarm system (SUDAL). The visualization function of safety assessment and environmental monitoring results is designed. This paper is to introduce the visualization design method using Geographic Information System (GIS) for SITES

Monitoring well design and sampling techniques at NAPL sites

International Nuclear Information System (INIS)

Collins, M.; Rohrman, W.R.; Drake, K.D.

1992-01-01

The existence of Non-Aqueous Phase Liquids (NAPLs) at many Superfund and RCRA hazardous waste sites has become a recognized problem in recent years. The large number of sites exhibiting this problem results from the fact that many of the most frequently used industrial solvents and petroleum products can exist as NAPLs. Hazardous waste constituents occurring as NAPLs possess a common characteristic that causes great concern during groundwater contamination evaluation: while solubility in water is generally very low, it is sufficient to cause groundwater to exceed Maximum Contamination Levels (MCLs). Thus, even a small quantity of NAPL within a groundwater regime can act as a point source with the ability to contaminate vast quantities of groundwater over time. This property makes it imperative that groundwater investigations focus heavily on characterizing the nature, extent, and migration pathways of NAPLs at sites where it exists. Two types of NAPLs may exist in a groundwater system. Water-immiscible liquid constituents having a specific gravity greater than one are termed Dense Non-Aqueous Phase Liquids, while those with a specific gravity less than one are considered Light Non-Aqueous Phase Liquids. For a groundwater investigation to properly characterize the two types of NAPLs, careful consideration must be given to the placement and sampling of groundwater monitoring wells. Unfortunately, technical reviewers at EPA Region VII and the Corps of Engineers find that many groundwater investigations fall short in characterizing NAPLs because several basic considerations were overlooked. Included among these are monitoring well location and screen placement with respect to the water table and significant confining units, and the ability of the well sampling method to obtain samples of NAPL. Depending on the specific gravity of the NAPL that occurs at a site, various considerations can substantially enhance adequate characterization of NAPL contaminants

Toehold-mediated strand displacement reaction-dependent fluorescent strategy for sensitive detection of uracil-DNA glycosylase activity.

Science.gov (United States)

Wu, Yushu; Wang, Lei; Jiang, Wei

2017-03-15

Sensitive detection of uracil-DNA glycosylase (UDG) activity is beneficial for evaluating the repairing process of DNA lesions. Here, toehold-mediated strand displacement reaction (TSDR)-dependent fluorescent strategy was constructed for sensitive detection of UDG activity. A single-stranded DNA (ssDNA) probe with two uracil bases and a trigger sequence were designed. A hairpin probe with toehold domain was designed, and a reporter probe was also designed. Under the action of UDG, two uracil bases were removed from ssDNA probe, generating apurinic/apyrimidinic (AP) sites. Then, the AP sites could inhibit the TSDR between ssDNA probe and hairpin probe, leaving the trigger sequence in ssDNA probe still free. Subsequently, the trigger sequence was annealed with the reporter probe, initiating the polymerization and nicking amplification reaction. As a result, numerous G-quadruplex (G4) structures were formed, which could bind with N-methyl-mesoporphyrin IX (NMM) to generate enhanced fluorescent signal. In the absence of UDG, the ssDNA probe could hybridize with the toehold domain of the hairpin probe to initiate TSDR, blocking the trigger sequence, and then the subsequent amplification reaction would not occur. The proposed strategy was successfully implemented for detecting UDG activity with a detection limit of 2.7×10 -5 U/mL. Moreover, the strategy could distinguish UDG well from other interference enzymes. Furthermore, the strategy was also applied for detecting UDG activity in HeLa cells lysate with low effect of cellular components. These results indicated that the proposed strategy offered a promising tool for sensitive quantification of UDG activity in UDG-related function study and disease prognosis. Copyright © 2016 Elsevier B.V. All rights reserved.

Berm design to reduce risks of catastrophic slope failures at solid waste disposal sites.

Science.gov (United States)

De Stefano, Matteo; Gharabaghi, Bahram; Clemmer, Ryan; Jahanfar, M Ali

2016-11-01

Existing waste disposal sites are being strained by exceeding their volumetric capacities because of exponentially increasing rates of municipal solid waste generation worldwide, especially in densely populated metropolises. Over the past 40 years, six well-documented and analyzed disposal sites experienced catastrophic failure. This research presents a novel analysis and design method for implementation of a series of in-situ earth berms to slow down the movement of waste material flow following a catastrophic failure. This is the first study of its kind that employs a dynamic landslide analysis model, DAN-W, and the Voellmy rheological model to approximate solid waste avalanche flow. A variety of single and multiple berm configuration scenarios were developed and tested to find an optimum configuration of the various earth berm geometries and number of berms to achieve desired energy dissipation and reduction in total waste material runout length. The case study application of the novel mitigation measure shows that by constructing a series of six relatively inexpensive 3 m high earth berms at an optimum distance of 250 m from the slope toe, the total runout length of 1000 m and associated fatalities of the Leuwigajah dumpsite catastrophic failure in Bandung, Indonesia, could have been reduced by half. © The Author(s) 2016.

Supercollider: Design changes

International Nuclear Information System (INIS)

Anon.

1990-01-01

A major task faced by the new US Superconducting Supercollider (SSC) Laboratory as it began life early last year was to prepare a baseline design, cost and schedule for the site in Ellis County, Texas. The conceptual design developed by the SSC Central Design Group at Berkeley in 1986 was for a generic site, and served as the basis of the cost estimate submitted to Congress for fiscal year 1990. Under the terms of the contract between Universities Research Association (URA - the SSC parent organization) and the US Department of Energy to establish the SSC Laboratory, signed in January 1989, a report on the SiteSpecific Conceptual Design Report was complete by December

Supercollider: Design changes

Energy Technology Data Exchange (ETDEWEB)

Anon.

1990-04-15

A major task faced by the new US Superconducting Supercollider (SSC) Laboratory as it began life early last year was to prepare a baseline design, cost and schedule for the site in Ellis County, Texas. The conceptual design developed by the SSC Central Design Group at Berkeley in 1986 was for a generic site, and served as the basis of the cost estimate submitted to Congress for fiscal year 1990. Under the terms of the contract between Universities Research Association (URA - the SSC parent organization) and the US Department of Energy to establish the SSC Laboratory, signed in January 1989, a report on the SiteSpecific Conceptual Design Report was complete by December.

Could transit sites become some of our great public spaces?

DEFF Research Database (Denmark)

Lanng, Ditte Bendix

of the urban spaces of traffic segregation with regard to sensory and social qualities of different ways of embodied wayfaring. The discussion draws on ethnographic studies into journeys, which entangle at the transit site,as well as re-design studio experiments. These draw to the foreground of design...... social and cultural life. Third, I draw on my studies into journeys at the site to learn about the spatial practicings of the site and of the properties and possibilities of the urban space design. Fourth, I explore in written text and drawing re-design potentials. And last, I sum up propositions...... considerations the engagement between the wayfarer and the environment. The paper is structured in five sections. I set out by introducing the traffic segregated transit site. Second, I outline and argue for the design challenge: to re-design the transit site as an important public space – a central part of our...

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

International Nuclear Information System (INIS)

1994-01-01

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. Section 108 of Public Law 95-604 states that the US Department of Energy (DOE) shall ''select and perform remedial actions at the designated processing sites and disposal sites in accordance with the general standards'' prescribed by the EPA. Regulations governing the required remedial action at inactive uranium processing sites were promulgated by the EPA in 1983 and are contained in 40 CFR Part 192 (1993), Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. This document describes the radiological and physical parameters for the remedial action of the soil

Basic repository environmental assessment design basis, Richton Dome site

International Nuclear Information System (INIS)

1988-01-01

This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Gulf Interior Region at Richton Dome in Perry County, Mississippi. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7,020 canisters of defense high-level reprocessing waste and associated quantities of remote-and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1,000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $4.49 billion. Costs include those for the WHPF, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region and the relatively easy access to the site. Construction would require an estimated 6.25 years. Engineering factors and costs are not strongly influenced by environmental considerations. 52 refs., 24 figs., 20 tabs

Basic repository environmental assessment design basis, Davis Canyon site

International Nuclear Information System (INIS)

1984-01-01

This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Paradox Basin in Davis Canyon, Utah. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7,020 canisters of defense high-level reprocessing waste and associated quantities of remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1,000-year-life carbon-steel waste packages in a collected waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $5.49 billion. Costs include those for the collocated WHPF, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region and the relatively sound nature of the salt at this site. Construction would require an estimated 7.75 years. Engineering factors and costs are not strongly influenced by environmental considerations. 50 refs., 24 figs., 20 tabs

Basic repository environmental assessment design basis, Lavender Canyon site

International Nuclear Information System (INIS)

1988-01-01

This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Paradox Basin in Lavender Canyon, Utah. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7020 canisters of defense high-level reprocessing waste and associated quantities of remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $5.51 billion. Costs include those for the collocated WHPP, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region and the relatively sound nature of the salt at this site. Construction would require an estimated 7.75 years. Engineering factors and costs are not strongly influenced by environmental considerations. 51 refs., 24 figs., 20 tabs

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho

International Nuclear Information System (INIS)

1991-09-01

The US Environmental Protection Agency (EPA) has established health and environmental regulations to correct and prevent groundwater contamination resulting from former uranium processing activities at inactive uranium processing sites (40 CFR 192). According to the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has decided that each assessment shall include information on hydrogeologic site characterization. The water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards is presented in Attachment 4. Site characterization activities discussed in this section include: Definition of the hydrogeologic characteristics of the environment, including hydrostratigraphy, aquifer parameters, areas of aquifer recharge and discharge, potentiometric surfaces, and groundwater velocities. Definition of background groundwater quality and comparison with the proposed EPA groundwater protection standards. Evaluation of the physical and chemical characteristics of the contaminant source and/or residual radioactive materials. Definition of existing groundwater contamination by comparison with the EPA groundwater protection standards. Description of the geochemical processes that affect the downward migration of the source contaminants at the processing site. Description of water resource utilization, including availability, current and future use and value, and alternate water supplies

Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

International Nuclear Information System (INIS)

1993-01-01

This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz

A design study for the isolation of the 281-3H retention basin at the Savannah River Site using the viscous liquid barrier technology

International Nuclear Information System (INIS)

Moridis, G.J.; Persoff, P.; Apps, J.; James, A.; Oldenburg, C.; McGrath, A.; Myer, L.; Pellerin, L.; Pruess, K.

1996-11-01

This report is a description of the design study for a pilot-scale field demonstration of the Viscous Liquid Barrier (VLB) technology, a new subsurface containment technology for waste isolation using a new generation of barrier liquids. The demonstration site was Retention Basin 281-3H, a shallow catchment basin at the Savannah River Site, which is contaminated mainly by radionuclides ( 137 Cs, 90 Sr, and 238 Pu). The goals of the field demonstration were (a) to demonstrate the ability to create a continuous subsurface barrier in order to isolate the contaminants, and (b) to demonstrate the continuity, performance, and integrity of the barrier. The site was characterized, and preliminary hydraulic conductivity data were obtained from core samples. Based on the site characteristics and the functional requirements, a conceptual model was developed, the barrier specifications were defined, and lance injection was selected as the emplacement method. The injection strategy for the subsurface conditions at the site was determined using numerical simulations. An appropriate variant of Colloidal Silica (CS) was selected as the barrier liquid based on its relative insensitivity to interactions with the site soils, and the formulation for optimum site performance was determined. A barrier verification strategy, including hydraulic, pneumatic, tracer, and geophysical methods, was developed. A lance water injection test was conducted in order to obtain representative estimates of the hydraulic conductivity and its distribution for the design of the barrier emplacement. The water injection test demonstrated the lack of permeable zones for CS injection, and a decision not to proceed with the barrier emplacement was reached

National Ignition Facility site requirements

International Nuclear Information System (INIS)

1996-07-01

The Site Requirements (SR) provide bases for identification of candidate host sites for the National Ignition Facility (NIF) and for the generation of data regarding potential actual locations for the facilities. The SR supplements the NIF Functional Requirements (FR) with information needed for preparation of responses to queries for input to HQ DOE site evaluation. The queries are to include both documents and explicit requirements for the potential host site responses. The Sr includes information extracted from the NIF FR (for convenience), data based on design approaches, and needs for physical and organization infrastructure for a fully operational NIF. The FR and SR describe requirements that may require new construction or may be met by use or modification of existing facilities. The SR do not establish requirements for NIF design or construction project planning. The SR document does not constitute an element of the NIF technical baseline

Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, horizontal emplacement mode: Volume 2

International Nuclear Information System (INIS)

1987-12-01

Chapter 6 discusses the repository design features and operating procedures that will be used to ensure compliance with regulatory limits for preclosure releases, performance objectives for waste retrieval, and performance objectives for post closure or long-term waste isolation. Chapter 7 discusses the analyses that were conducted in developing the repository design and the impacts of various external factors on the design of repository elements and the repository as a whole. These discussions are divided into preclosure design analysis, post closure design analysis, and engineering analysis of design. Also discussed are the structures, systems, and components that have been identified as important to safety and the barriers that have been, or need to be, identified as important to waste isolation. Chapter 8 discusses the engineering design information needs that were identified during conceptual design as necessary to advance the current conceptual design to Licence Application Design. These information needs should be resolved during the site characterization program or by other technology development studies. The discussion of these design issues and data needs is arranged according to the major elements of the repository. Chapter describes the quality assurance program. 146 refs., 40 figs., 22 tabs

Towards urban mobility designs

DEFF Research Database (Denmark)

Lanng, Ditte Bendix; Harder, Henrik; Jensen, Ole B.

2012-01-01

for the wayfarers who use the site. The data for our work concerns a transit site in the 1970s urban district of Aalborg Øst, Denmark. - We set out by introducing our approach to the site. - Second, we examine the functional layout of the transit site in Aalborg Øst and outline the design challenge which we......Functionalist traffic design aims at a rational organisation of movement from A to B in a segregated and uniform physical environment. Such urban areas have been criticized for being exclusively functional and lacking sensuous and social qualities. Recent research on mobilities challenges the more...... insights on functional urban planning, on embodied practices and experiences of wayfaring, and on concrete small scale design concerns. We emphasise an integrated design agenda for those ordinary transit sites which is concerned with functional issues as well as the quality of life on the ground...

Ecological restoration of Central European mining sites: a summary of a multi-site analysis

Energy Technology Data Exchange (ETDEWEB)

Prach, K.; Rehounkova, K.; Rehounek, J.; Konvalinkova, P. [University of South Bohemia, Ceske Budejovice (Czech Republic)

2011-07-01

Sites disturbed by mining were surveyed in the Czech Republic, central Europe. The sites included spoil heaps from coal mining, sand and gravel pits, extracted peatlands and stone quarries. The following main conclusions emerged: I) potential for spontaneous succession to be used in restoration projects is between 95 and 100% of the total area disturbed; ii) mining sites, if mining is properly designed and then the sites are left to spontaneous succession, often act as refugia for endangered and retreating organisms, and may contribute substantially to local biodiversity.

Nevada Test Site Environmental Report 2005, Attachment A - Site Description

International Nuclear Information System (INIS)

Cathy A. Wills

2006-01-01

This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report

Nevada Test Site Environmental Report 2005, Attachment A - Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2006-10-01

This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Basic repository environmental assessment design basis: Deaf Smith County site

International Nuclear Information System (INIS)

1988-03-01

This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Palo Duro Basin in Deaf Smith County, Texas. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7,020 canisters of defense high-level reprocessing waste and associated quantities or remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $4.64 billion. Costs include those for the collocate WHPF, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region, the relatively easy access to the site, and the relatively weak nature of the salt at this site. Construction would require an estimated 7 to 7.5 years. Engineering factors and costs are not strongly influenced by environmental considerations. 62 refs., 24 figs., 20 tabs

Designating Earth's Moon as a United Nations World Heritage Site - Permanently Protected from Commercial or Military Uses

Science.gov (United States)

Steiner, R. G.

2002-01-01

This paper proposes that Earth's Moon, in its entirety, be designated a United Nations World Heritage Site (WHS), permanently protected from any and all commercial or military utilization and reserved exclusively for scientific and aesthetic purposes. The paper discusses: 1) the extraordinary importance of the Moon for science, culture, and religion - past, present and future; 2) the history of proposals to exploit the Moon for commercial and military purposes and the shortcomings of this colonial, exploitation paradigm; and 3) the necessity, policy mechanisms, and political dynamics of designating the Moon as a World Heritage Site, permanently protected from commercial and/or military uses. The first part of the paper discusses the extraordinary importance of the Moon as it exists today - as a scientific laboratory, a source of beauty and inspiration throughout human evolution, a source for artistic expression, and as an object that is considered sacred by many cultures. Next, the paper traces the history of specific proposals for the exploitation of the Moon for commercial and/or military purposes - including plans by the U.S. Air Force in 1959 to detonate a nuclear explosion on the Moon, proposals to strip-mine the lunar regolith for helium-3 and rocket-fuel hydrogen; construction of solar power plants to transmit energy to Earth, and proposals to use the lunar surface as a billboard upon which to project commercial advertisements visible from Earth. The profound ethical, legal, and scientific shortcomings of this exploitation paradigm are described as an emerging Extraterrestrial Manifest Destiny that we have a collective obligation to challenge and constrain. The paper proposes that space exploration be infused with an ethical commitment to compassion, reverence, conservation, and non-interference to abiotic and biotic systems alike; as opposed to the expansion and extraterrestrial imposition of the colonization, exploitation, domination, and despoliation

Technology development for the design of waste repositories at arid sites: field studies of biointrusion and capillary barriers

International Nuclear Information System (INIS)

Nyhan, J.W.; Abeele, W.; Hakonson, T.; Lopez, E.A.

1986-03-01

The field research program involving the development of technology for arid shallow land burial (SLB) sites is described. Results of field testing of biointrusion barriers installed at an active low-level radioactive waste disposal site (Area G) at Los Alamos are presented. A second experiment was designed to test the ability of a capillary barrier to effectively convey water infiltrating a SLB trench around and away from underlying buried wastes. The performance of the capillary barrier was tested in the field for a barrier of known thickness (2 m), slope (10%), and slope length (2 m), and for one combination of porous materials [a crushed tuff-clay (2% w/w) mixture overlying Ottawa sand] subjected to a known water addition rate. The waste management implications of both studies are also discussed

Rational Catalyst Design of Titanium-Silica Materials Aided by Site-Specific Titration Tools

Science.gov (United States)

Eaton, Todd Robert

between particle and crystal size, as obtained from XRD. In the course of establishing these relationships we've gained the knowledge of how to control TiO x structure, which enables the design of new and better catalysts. Understanding the synthesis-structure-function relationships allow for the design of a tandem photo/thermocatalytic reaction system for producing and consuming H2O2. By partially overcoating a TiO 2 photocatalyst with a ˜2 nm silica layer we observe a 56-fold rate improvement compared to bare-TiO2 for H2O2 synthesis from the proton-assisted reduction of O2. Addition of metal-SiO2 thermocatalysts (metal=Ti, Nb, or Ta) with sites needed for H2O2 activation creates a tandem system wherein the H2O2 produced in situ is utilized for alkene epoxidation. Compared to a thermocatalytic-only system, the tandem system accelerates epoxidation for cis-cyclooctene(11x faster), styrene(20x) and 1-octene(30x). This approach demonstrates a means for epoxidation with O2 that avoids H2O2 purification and transport, simplifies the total process, provides new opportunities for control by independent H2O2 production and consumption in the same reactor, and enhances rates relative to thermocatalytic-only epoxidation by intimately coupling H2O2 generation and consumption. Critically, establishment of titanium-silica synthesis-structure-function relationships enables the design of new catalysts and systems that are less energy- and material-intensive, leading towards more sustainable chemistry.

Design parameters and source terms: Volume 1, Design parameters: Revision 0

International Nuclear Information System (INIS)

1987-10-01

The Design Parameters and Source Terms Document was prepared in accordance with DOE request and to provide data for the environmental impact study to be performed in the future for the Deaf Smith County, Texas site for a nuclear waste repository in salt. This document updates a previous unpublished report by Stearns Catalytic Corporation (SCC), entitled ''Design Parameters and Source Terms for a Two-Phase Repository in Salt,'' 1985, to the level of the Site Characterization Plan - Conceptual Design Report. The previous unpublished SCC Study identifies the data needs for the Environmental Assessment effort for seven possible Salt Repository sites

Cap stabilization for reclaimed uranium sites

International Nuclear Information System (INIS)

Abt, S.R.; Nelson, J.D.; Johnson, T.L.; Hawkins, E.F.

1989-01-01

The reclamation and stabilization of uranium-mill tailings sites requires engineering designs to protect against the disruption of tailings and the potential release of radioactive materials. The reclamation design is to be effective for 200-1000 years. This paper presents recently developed or refined techniques and methodologies used to evaluate uranium-tailings-reclamation plans designed to provide long-term stability against failure modes. Specific cap-design aspects presented include design flood selection, influence of fluvial geomorphology on site stabilization, stable slope prediction, slope stabilization using riprap, and riprap selection relative to rock quality and durability. Design relationships are presented for estimating flow through riprap, sizing riprap, and estimating riprap flow resistance for overtopping conditions. Guidelines for riprap-layer thickness and gradation are presented. A riprap-rating procedure for estimating rock quality and durability is also presented

ITER site selection studies in Spain

International Nuclear Information System (INIS)

Medrano, M.; Alejaldre, C.; Doncel, J.; Garcia, A.; Ibarra, A.; Jimenez, J.A.; Sanchez de Mora, M.A.; Alcala, F.; Diez, J.E.; Dominguez, M.; Albisu, F.

2003-01-01

The studies carried out to evaluate and select a candidate site for International Thermonuclear Experimental Reactor (ITER) construction in Spain are presented in this paper. The ITER design, completed in July 2001, considered a number of technical requirements that must be fulfilled by the selected site. Several assumptions concerning the ITER site were made in order to carry on the design before final site selection. In the studies undertaken for ITER site selection in Spain, the referred technical requirements and assumptions were applied across the whole of Spain and two areas were identified as being preferential. These areas are on the Mediterranean coast and are situated in the Catalan and Valencian regions. A comparative evaluation based on technical characteristics for the concrete plots, proposed within the preferential areas, has been done. The result of these studies was the selection of a site that was deemed to be the most competitive--Vandellos (Tarragona)--and it was proposed to the European Commission for detailed studies in order to be considered as a possible European site for ITER construction. Another key factor for hosting ITER in Spain, is the licensing process. The present status is summarised in this paper

Nevada National Security Site Environmental Report 2013

Energy Technology Data Exchange (ETDEWEB)

Wills, C.

2014-09-09

This report was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) (formerly designated as the Nevada Site Office [NNSA/NSO]). The new field office designation occurred in March 2013. Published reports cited in this 2013 report, therefore, may bear the name or authorship of NNSA/NSO. This and previous years’ reports, called Annual Site Environmental Reports (ASERs), Nevada Test Site Environmental Reports (NTSERs), and, beginning in 2010, Nevada National Security Site Environmental Reports (NNSSERs), are posted on the NNSA/NFO website at http://www.nv.energy.gov/library/publications/aser.aspx.

Multi-Site Project Management A Program for Reducing the Cost of Technology Deployment at Department of Energy Sites

International Nuclear Information System (INIS)

Davis, N.R.; Selden, E.R.; Little, D.B.; Coleman, M.C.; Bennett, J.T.

2009-01-01

Retrieval and processing of High Level Waste (HLW) stored in Department of Energy (DOE) waste tanks is performed to support closure of the tanks as required by site specific regulatory agreements. Currently, there are four sites in the DOE Complex that have HLW tanks and must process and disposition HLW. As such, there is an opportunity to achieve an economy of scale and reduce duplication of efforts. Two or more sites typically have similar technology development and deployment needs. Technology development is already executed at the national level. As the technology is matured, the next step is to commission a design/build project. Typically each site performs this separately due to differences in waste type, tank design, site specific considerations such as proximity to the water table or to the site boundary. The focus of the individual sites tends to be on the differences between sites versus on the similarities thus there is an opportunity to minimize the cost for similar deployments. A team of engineers and project management professionals from the Savannah River Site has evaluated technology needs at the four HLW sites and determined that there is an economy of scale that can be achieved by specific technology deployments in the area of waste retrieval, waste pretreatment and waste disposition. As an example, the Waste on Wheels tank retrieval system (presented in the 2006 Waste Management Symposium) was designed and fabricated in portable modules that could be installed in HLW tanks at Hanford, Savannah River or Idaho. This same concept could be used for modular in-tank cesium removal process and equipment, tank cleaning mechanical equipment, and chemical tank cleaning process and equipment. The purpose of this paper is to present a multi-site project management approach that will reduce deployment costs and be consistent with DOE Order 413.3 project management principles. The approach will describe how projects can be managed by a lead site with

Site locality identification study: Hanford Site. Volume I. Methodology, guidelines, and screening

International Nuclear Information System (INIS)

1980-07-01

Presented in this report are the results of the site locality identification study for the Hanford Site using a screening process. To enable evaluation of the entire Hanford Site, the screening process was applied to a somewhat larger area; i.e., the Pasco Basin. The study consisted of a series of screening steps that progressively focused on smaller areas which are within the Hanford Site and which had a higher potential for containing suitable repository sites for nuclear waste than the areas not included for further study. Five site localities, designated H-1, H-2, H-3, H-4, H-5 (Figure A), varying in size from approximately 10 to 50 square miles, were identified on the Hanford Site. It is anticipated that each site locality may contain one or more candidate sites suitable for a nuclear waste repository. The site locality identification study began with definition of objectives and the development of guidelines for screening. Three objectives were defined: (1) maximize public health and safety; (2) minimize adverse environmental and socioeconomic impacts; and (3) minimize system costs. The screening guidelines have numerical values that provided the basis for the successive reduction of the area under study and to focus on smaller areas that had a higher likelihood of containing suitable sites

Geochemical investigation of UMTRAP designated site at Salt Lake City, Utah

International Nuclear Information System (INIS)

Markos, G.; Bush, K.J.

1983-09-01

This report is the result of a geochemical investigation of the former uranium mill and tailings site at Salt Lake City, Utah. This is one in a series of site specific geochemical investigations performed on the inactive uranium mill tailings included in the Uranium Mill Tailings Remedial Action Project. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results will be used to model contaminant migration and to develop criteria for long-term containment media such as a cover system which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. The solid samples were water extracted to remove easily soluble salts and acid extracted to remove carbonates and hydroxides. The water extracts and solid samples were anlyzed for the major and trace elements. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Four major conclusions are: (1) sediments in the ditches and creeks adjacent to the site contain tailings, however, the waters were generally not contaminated; (2) tailings are mixed with the soils within a meter below the tailings in some locations, however, water-soluble contaminants decrease to below background levels within 30 cm below the tailings; (3) there has not been significant acid seepage into the soils below the tailings; and (4) salt crusts on the tailings contain trace elements, with the elements that form chloride complexes having the greatest accumulation

Nevada Test Site Environmental Report 2007 Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2008-09-01

This appendix expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Site selection handbook: Workshop on site selection for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

1987-10-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires the Department of Energy (DOE) to provide technical assistance to ''...those compact regions, host States and nonmember States determined by the Secretary to require assistance.'' Technical assistance has been defined to include, but not be limited to, ''technical guidelines for site selection.'' This site selection workshop was developed to assist States and Compacts in developing new low-level radioactive waste (LLW) disposal sites in accordance with the requirements of the LLRWPAA. The workshop comprises a series of lectures, discussion topics, and exercises, supported by this Site Selection Workshop Handbook, designed to examine various aspects of a comprehensive site selection program. It is not an exhaustive treatment of all aspects of site selection, nor is it prescriptive. The workshop focuses on the major elements of site selection and the tools that can be used to implement the site selection program

Savannah River Site reactor hardware design modification study

International Nuclear Information System (INIS)

Fisher, J.E.

1990-03-01

A study was undertaken to assess the merits of proposed design modifications to the SRS reactors. The evaluation was based on the responses calculated by the RELAP5 systems code to double-ended guillotine break loss-of-coolant-accidents (DEGB LOCAs). The three concepts evaluated were (a) elevated plenum inlet piping with a guard vessel and clamshell enclosures, (b) closure of both rotovalves in the affected loop, and (c) closure of the pump suction valve in the affected loop. Each concept included a fast reactor shutdown (to 65% power in 100 ms) and a 2-s ac pump trip. For the elevated piping design, system recovery was predicted for breaks in the plenum inlet or pump suction piping; response to the pump discharge break location did not show improvement compared to the present system configuration. The rotovalve closure design improved system response to plenum inlet or pump discharge breaks; recovery was not predicted for pump suction breaks. The pump suction valve closure design demonstrated system recovery for all break locations downstream of the valve. A combination of features is recommended to ensure liquid inventory recovery for all break locations. The elevated piping design performance during pump discharge breaks would be improved with addition of a dc pump trip in the affected loop. Valve closure design performance for a break location in the short section of piping between the reactor concrete shield and the pump suction valve would benefit from the clamshell enclosing that section of piping. 12 refs., 10 figs., 2 tabs

Air quality measurements for site characterization

International Nuclear Information System (INIS)

Carter, M.W.; Conklin, W.C.

1982-01-01

Effective and timely site characterization is an important part of selecting a site for low-level waste disposal. Parameters measured can be compared with pertinent regulatory requirements, used for a reference base, helpful in evaluating environmental impacts, utilized in documenting changes in control programs, of value in modeling studies and other data uses, and beneficial in providing relevant sampling and methodology training. This paper will focus on specific air quality measurements which should be an inherent part of the site characterization program. The program is designed to measure, quantify, and identify contributions from site uses (operational procedures), atmospheric fallout, natural radioactivity, and vicinity and regional applications of radionuclides. The recommended air quality measurements program will be described in association with a reference site developd by the US Nuclear Regulatory Commission. Particular attention will be devoted to the type and quality of information which is needed, the scope of sampling and measurements, the frequency of measurements, locations and numbers of sampling stations, the period of time needed for site characterization, and the proper uses of the information once it has been obtained. Adequate characterization of the site will be most important in final site selection and in the operation of the site as to periodically assessing environmental impacts and helping guide any remedial control efforts designed to meet regulatory requirements

Social Networking Sites in the Classroom: Unveiling New Roles for Teachers and New Approaches to Online Course Design

Directory of Open Access Journals (Sweden)

Jorge Eduardo Pineda Hoyos

2014-12-01

Full Text Available Web 2.0 tools in general and social networking sites in particular are very popular today in everyday life. However, their use in education has not been explored. This paper reports the findings of the implementation of a web 2.0 tool namely a social networking site as a web support for a face-to-face course. The findings show that the implementation of a web-based environment in a face-to-face course can be viewed from 5 different managerial areas: (1 logistics management, (2 information/knowledge management, (3 communication management, (4 class work extension management and (5 web-based environment easiness of accessibility. The conclusions of the study show that the implementation of the web-based environment unveils new roles for teachers and new approaches to design online or blended courses.

Nevada National Security Site Environmental Report 2011 Attachment A: Site Description

International Nuclear Information System (INIS)

Wills, Cathy

2012-01-01

This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2011. Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NNSS. The NNSS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NNSS operations. These key features include the general remote location of the NNSS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

A 2-deoxyribonolactone-containing nucleotide: Isolation and characterization of the alkali-sensitive photoproduct of the trideoxyribonucleotide d(ApCpA)

International Nuclear Information System (INIS)

Urata, H.; Yamamoto, K.; Akagi, M.; Hiroaki, H.; Uesugi, S.

1989-01-01

It has been reported that ACA sequences in DNA are mutagenic hot spots in UV-induced mutagenesis and are sites of an alkali-sensitive lesion produced by UV irradiation. In order to characterize the UV-induced lesion of an ACA site, chemically synthesized trideoxyribonucleotide d(ApCpA) was irradiated with UV light and the alkali-sensitive photoproduct was isolated. The structure of this photoproduct was characterized as the trinucleotide containing 2-deoxyribonolactone at the internal residue by 2D DQF-COSY, FT-IR, FAB-MS, and chemical properties. It is known that this lesion is also produced by gamma-irradiation, neocarzinostatin, the 1,10-phenanthroline-copper complex, and hydrogen peroxide and is highly mutagenic because of its resistance to cleavage by certain apurinic/apyrimidinic (AP) endonucleases. Thus, 2-deoxyribonolactone may be one of the lethal DNA lesions induced by UV irradiation to organisms and one of the intermediates of UV-induced DNA strand breaks because the DNA strand is cleaved at this site with beta- and subsequent delta-elimination mechanisms

Lessons learned -- a comparison of the proposed on-site waste management facilities at the various Department of Energy sites

International Nuclear Information System (INIS)

Ciocco, J.; Singh, D.; Survochak, S.; Elo, M.

1996-01-01

The Department of Energy Sites (DOE) are faced with the challenge of managing several categories of waste generated from past or future cleanup activities, such as 11(e)2 byproduct material, low-level radioactive (LL), low-level radioactive mixed (LLM), transuranic (TRU), high level radioactive (HL), and hazardous waste (HW). DOE must ensure safe and efficient management of these wastes while complying with all applicable federal and state laws. Proposed waste management strategies for the EM-40 Environmental Restoration (ER) program at these sites indicate that on-site disposal is becoming a viable option. For purposes of this paper, on-site disposal cells managed by the EM-40 program at Hanford, Weldon Spring, Fernald Environmental Management Project (FEMP) and Rocky Flats were compared. Programmatic aspects and design features were evaluated to determine what comparisons can be made, and to identify benefits lessons learned that may be applicable to other sites. Based on comparative analysis, it can be concluded that the DOE EM-40 disposal cells are very unique. Stakeholders played a major role in the decision to locate the various DOE on-site disposal facilities. The disposal cells will be used to manage 11(e)2 by-product materials, LL, LLM, and/or HLW. The analysis further suggests that the design criteria are comparable. Lessons learned relative to the public involvement activities at Weldon Spring, and the design approach at Hanford should be considered when planning future on-site disposal facilities at DOE sites. Further, a detailed analysis of progress made at Hanford should be evaluated for application at sites such as Rocky Flats that are currently planning on-site disposal facilities

American National Standard: guidelines for evaluating site-related geotechnical parameters at nuclear power sites

International Nuclear Information System (INIS)

Anon.

1978-01-01

This standard presents guidelines for evaluating site-related geotechnical parameters for nuclear power sites. Aspects considered include geology, ground water, foundation engineering, and earthwork engineering. These guidelines identify the basic geotechnical parameters to be considered in site evaluation, and in the design, construction, and performance of foundations and earthwork aspects for nuclear power plants. Also included are tabulations of typical field and laboratory investigative methods useful in identifying geotechnical parameters. Those areas where interrelationships with other standards may exist are indicated

Site Identification by Ligand Competitive Saturation (SILCS) simulations for fragment-based drug design.

Science.gov (United States)

Faller, Christina E; Raman, E Prabhu; MacKerell, Alexander D; Guvench, Olgun

2015-01-01

Fragment-based drug design (FBDD) involves screening low molecular weight molecules ("fragments") that correspond to functional groups found in larger drug-like molecules to determine their binding to target proteins or nucleic acids. Based on the principle of thermodynamic additivity, two fragments that bind nonoverlapping nearby sites on the target can be combined to yield a new molecule whose binding free energy is the sum of those of the fragments. Experimental FBDD approaches, like NMR and X-ray crystallography, have proven very useful but can be expensive in terms of time, materials, and labor. Accordingly, a variety of computational FBDD approaches have been developed that provide different levels of detail and accuracy.The Site Identification by Ligand Competitive Saturation (SILCS) method of computational FBDD uses all-atom explicit-solvent molecular dynamics (MD) simulations to identify fragment binding. The target is "soaked" in an aqueous solution with multiple fragments having different identities. The resulting computational competition assay reveals what small molecule types are most likely to bind which regions of the target. From SILCS simulations, 3D probability maps of fragment binding called "FragMaps" can be produced. Based on the probabilities relative to bulk, SILCS FragMaps can be used to determine "Grid Free Energies (GFEs)," which provide per-atom contributions to fragment binding affinities. For essentially no additional computational overhead relative to the production of the FragMaps, GFEs can be used to compute Ligand Grid Free Energies (LGFEs) for arbitrarily complex molecules, and these LGFEs can be used to rank-order the molecules in accordance with binding affinities.

SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

International Nuclear Information System (INIS)

Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

1977-01-01

1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability

SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

Energy Technology Data Exchange (ETDEWEB)

Frigerio, N A [Environmental Impact Studies, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Habegger, L J; King, R F; Hoover, L J [Energy and Environmental Systems Division, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Clark, N A [Applied Mathematics Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Cobian, J M [Northwestern University, Evanston, Illinois 60201 (United States)

1977-08-01

1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability.

Cultivating Collaborations: Site Specific Design for Embodied Science Learning.

Science.gov (United States)

Gill, Katherine; Glazier, Jocelyn; Towns, Betsy

2018-05-21

Immersion in well-designed outdoor environments can foster the habits of mind that enable critical and authentic scientific questions to take root in students' minds. Here we share two design cases in which careful, collaborative, and intentional design of outdoor learning environments for informal inquiry provide people of all ages with embodied opportunities to learn about the natural world, developing the capacity for understanding ecology and the ability to empathize, problem-solve and reflect. Embodied learning, as facilitated by and in well-designed outdoor learning environments, leads students to develop new ways of seeing, new scientific questions, new ways to connect with ideas, with others and new ways of thinking about the natural world. Using examples from our collaborative practices as experiential learning designers, we illustrate how creating the habits of mind critical to creating scientists, science-interested, and science-aware individuals benefits from providing students spaces to engage in embodied learning in nature. We show how public landscapes designed in creative partnerships between educators, scientists, designers and the public have potential to amplify science learning for all.

Design parameters and source terms: Volume 1, Design parameters: Revision 0

International Nuclear Information System (INIS)

1987-09-01

The Design Parameters and Source Terms Document was prepared in accordance with DOE request and to provide data for the environmental impact study to be performed in the future for the Deaf Smith County, Texas site for a nuclear waste repository in salt. This document updates a previous unpublished report to the level of the Site Characterization Plan - Conceptual Design Report, SCP-CDR. The previous unpublished SCC Study identified the data needs for the Environmental Assessment effort for seven possible salt repository sites

Security scanning of Web sites at CERN

CERN Multimedia

IT Department

2010-01-01

As of early 2010, the CERN Computer Security Team will start regular scanning of all Web sites and Web applications at CERN, visible on the Internet, or on the General Purpose Network (office network). The goal of this scanning is to improve the quality of CERN Web sites. All deficits found will be reported by e-mail to the relevant Web site owners, and must be fixed in a timely manner. Web site owners may also request one-off scans of their Web site or Web application, by sending an e-mail to Computer.Security@cern.ch. These Web scans are designed to limit the impact on the scanned Web sites. Nevertheless, in very rare cases scans may cause undesired side-effects, e.g. generate a large number of log entries, or cause particularly badly designed or less robust Web applications to crash. If a Web site is affected by these security scans, it will also be susceptible to any more aggressive scan that can be performed any time by a malicious attacker. Such Web applications should be fixed, and also additionally...

Lack of association between the APEX1 Asp148Glu polymorphism and sporadic amyotrophic lateral sclerosis.

Science.gov (United States)

Coppedè, Fabio; Lo Gerfo, Annalisa; Carlesi, Cecilia; Piazza, Selina; Mancuso, Michelangelo; Pasquali, Livia; Murri, Luigi; Migliore, Lucia; Siciliano, Gabriele

2010-02-01

Impairments in DNA repair enzymes have been observed in amyotrophic lateral sclerosis (ALS) tissues, particularly in the activity of the apurinic/apyrimidinic endonuclease 1 (APEX1). Moreover, it was suggested that the common APEX1 Asp148Glu polymorphism might be associated with ALS risk. To further address this question we performed the present study aimed at evaluating the contribution of the APEX1 Asp148Glu polymorphism in sporadic ALS (sALS) risk and clinical presentation, including age and site of onset and disease progression. We screened 134 sALS Italian patients and 129 matched controls for the presence of the APEX1 Asp148Glu polymorphism. No difference in APEX1 Asp148Glu allele and genotype frequencies was found between the groups, nor was the polymorphism associated with age and site of onset or disease progression. Present results do not support a role for the APEX1 Asp148Glu polymorphism in sALS pathogenesis in the Italian population.

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

International Nuclear Information System (INIS)

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed.

Basic repository environment assessment design basis, Cypress Creek Dome Site

International Nuclear Information System (INIS)

1988-03-01

This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Gulf Interior Region at Cypress Creek Cone, Mississippi. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7020 canisters of defense high-level reprocessing waste and associated quantities of remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $4.66 billion. Costs include those for the collocated WHPF, engineering, and contingency, but exclude waste from assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relatively easy access to the site. Construction would require an estimated 7 years. Engineering factors and costs are not strongly influenced by environmental considerations. 53 refs., 24 figs., 10 tabs

Spectral Shapes for accelerograms recorded at rock sites

International Nuclear Information System (INIS)

Ghosh, A.K.; Muralidharan, N.; Sharma, R.D.

1986-01-01

Earthquake accelerograms recorded on rock sites have been analysed to develop site-specific response spectra for use in aseismic design. Normalized pseudo absolute acceleration spectra for various values of damping, pertinent to nuclear power plant design in particular are presented. Various ground motion parameters, viz. peak displacement, velocity acceleration (including v/a, ad/v 2 and the ratios of the three orthogonal components) for fifty four accelerograms are examined through motion time histories to be used in structural response analysis. The analysis presented in this paper aims at specifying site specific response spectra for earthquake resistant design of structures and generation of spectrum compatible accelerograms. The salient features of the data set have been discussed. (author)

Design and Construction of Deinococcus Radiodurans for Biodegradation of Organic Toxins at Radioactive DOE Waste Sites

International Nuclear Information System (INIS)

Daly, Michael J.; Wackett, Lawrence P.; Fredrickson, James K.

2001-01-01

Seventy million cubic meters of ground and three trillion liters of groundwater have been contaminated by leaking radioactive waste generated in the United States during the Cold War. A cleanup technology is being developed based on the extremely radiation resistant bacterium Deinococcus radiodurans that is being engineered to express bioremediating functions. Research aimed at developing D. radiodurans for organic toxin degradation in highly radioactive waste sites containing radionuclides, heavy metals, and toxic organic compounds was started by this group.Work funded by the existing grant has already contributed to eleven papers on the fundamental biology of D. radiodurans and its design for bioremediation of highly radioactive waste environments

Mock Site Licensing Demonstration Project. Final report

International Nuclear Information System (INIS)

Roop, R.D.

1986-06-01

The Mock Site Licensing Demonstration Project developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This report describes the development, contant, and usefulness of the siting simulation. The simulation was designed by Harvard University's Program on Negotiation; it can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions. In the first, participants negotiate the selection of siting criteria, and in the second, a preferred site for a facility is chosen from three candidate sites. The project sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation was conducted for persons involved in planning for LLW. It is concluded that the siting simulation can be useful in three ways: (1) as a tool for information dissemination, (2) as a vehicle that can foste communication among parties in conflict, and (3) as a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

Early Site Permit Demonstration Program: Plant parameters envelope report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

The Early Site Permit (ESP) Demonstration Program is the nuclear industry`s initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants.

Kansei Engineering and Website Design

DEFF Research Database (Denmark)

Song, Zheng; Howard, Thomas J.; Achiche, Sofiane

2012-01-01

a methodology based on Kansei Engineering, which has done significant work in product and industrial design but not quite been adopted in the IT field, in order to discover implicit emotional needs of users toward web site and transform them into design details. Survey and interview techniques and statistical...... methods were performed in this paper. A prototype web site was produced based on the Kansei results integrated with technical expertise and practical considerations. The results showed that the Kansei Engineering methodology in this paper played a significant role in web site design in terms of satisfying......Capturing users’ needs is critical in web site design. However, a lot of attention has been paid to enhance the functionality and usability, whereas much less consideration has been given to satisfy the emotional needs of users, which is also important to a successful design. This paper explores...

Nevada National Security Site Environmental Report 2011 Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed.

2012-09-12

This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2011. Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NNSS. The NNSS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NNSS operations. These key features include the general remote location of the NNSS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

Remedial Action Plan and site conceptual design for stabilization of the inactive uranium mill tailings site at Spook, Wyoming

Energy Technology Data Exchange (ETDEWEB)

Matthews, M L [USDOE Albuquerque Operations Office, NM (United States). Uranium Mill Tailings Remedial Action Project Office; Sullivan, M [Wyoming State Government, Cheyenne, WY (United States)

1990-04-01

This Remedial Action Plan (RAP) has been developed to serve a threefold purpose. It presents the series of activities which are proposed by the US Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at an inactive uranium processing site northeast of Casper, Wyoming, and referred to as the Spook site. It provides a characterization of the present conditions at the site and also serves to document the concurrence of the State of Wyoming and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the State of Wyoming, and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement.

Remedial Action Plan and site conceptual design for stabilization of the inactive uranium mill tailings site at Spook, Wyoming

International Nuclear Information System (INIS)

Matthews, M.L.

1990-04-01

This Remedial Action Plan (RAP) has been developed to serve a threefold purpose. It presents the series of activities which are proposed by the US Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at an inactive uranium processing site northeast of Casper, Wyoming, and referred to as the Spook site. It provides a characterization of the present conditions at the site and also serves to document the concurrence of the State of Wyoming and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the State of Wyoming, and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement

Volunteers Oriented Interface Design for the Remote Navigation of Rescue Robots at Large-Scale Disaster Sites

Science.gov (United States)

Yang, Zhixiao; Ito, Kazuyuki; Saijo, Kazuhiko; Hirotsune, Kazuyuki; Gofuku, Akio; Matsuno, Fumitoshi

This paper aims at constructing an efficient interface being similar to those widely used in human daily life, to fulfill the need of many volunteer rescuers operating rescue robots at large-scale disaster sites. The developed system includes a force feedback steering wheel interface and an artificial neural network (ANN) based mouse-screen interface. The former consists of a force feedback steering control and a six monitors’ wall. It provides a manual operation like driving cars to navigate a rescue robot. The latter consists of a mouse and a camera’s view displayed in a monitor. It provides a semi-autonomous operation by mouse clicking to navigate a rescue robot. Results of experiments show that a novice volunteer can skillfully navigate a tank rescue robot through both interfaces after 20 to 30 minutes of learning their operation respectively. The steering wheel interface has high navigating speed in open areas, without restriction of terrains and surface conditions of a disaster site. The mouse-screen interface is good at exact navigation in complex structures, while bringing little tension to operators. The two interfaces are designed to switch into each other at any time to provide a combined efficient navigation method.

Geohydrology of industrial waste disposal site

International Nuclear Information System (INIS)

Gaynor, R.K.

1984-01-01

An existing desert site for hazardous chemical and low-level radioactive waste disposal is evaluated for suitability. This site is characterized using geologic, geohydrologic, geochemical, and other considerations. Design and operation of the disposal facility is considered. Site characteristics are also evaluated with respect to new and proposed regulatory requirements under the Resource Conservation and Recovery Act (1976) regulations, 40 CFR Part 264, and the ''Licensing Requirements for Landfill Disposal of Radioactive Waste,'' 10 CRF Part 61. The advantages and disadvantages of siting new disposal facilities in similar desert areas are reviewed and contrasted to siting in humid locations

Geochemical investigation of UMTRAP designated site at Grand Junction, Colorado

International Nuclear Information System (INIS)

Markos, G.; Bush, K.J.

1983-09-01

This report is the result of a geochemical investigation of the former uranium mill and tailings site at Grand Junction, Colorado. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results should be used to model contaminant migration and to develop criteria for long-term containment media, such as a cover system which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a sampling of waters in two seasons and solid material from the background, the area adjacent to the site, and the site. The solid samples were water extracted to remove easily soluble salts and acid extracted to remove carbonates and hydroxides. The water extracts and solid samples were analyzed for the major and trace elements. A limited number of samples were analyzed for radiological components. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Four major conclusions are: (1) trace element concentrations in shallow subsurface waters adjacent to the tailings temporally vary up to an order of magnitude; (2) the riverbank soils and borehole waters are contaminated with uranium, radium, and trace elements from discharge of tailings solids and solutions during the active time of the mill; however, the movement of contaminants toward the Colorado River does not appear to be significant; (3) the Colorado River adjacent to the tailings is not contaminated; and (4) trace metals have accumulated at both the tailings/cover and tailings/soil interface because of precipitation reactions caused by chemical differences between the two materials

Environmental assessment, Richton Dome site, Mississippi

International Nuclear Information System (INIS)

1986-05-01

The Nuclear Waste Policy Act of 1982 (42 USC Sections 10101-10226) requires the environmental assessment of a potential site to include a statement of the basis for the nomination of a site as suitable for characterization. Volume 2 of this environmental assessment provides a detailed evaluation of the Richton Dome Site and its suitability as the site for a radioactive waste disposal facility under DOE siting guidelines, as well as a comparison of the Richton Dome site with other proposed sites. Evaluation of the Richton Dome site is based on the reference repository design, but the evaluation will not change if based on the Mission Plan repository concept. The comparative evaluation of proposed sites is required under DOE guidelines, but is not intended to directly support the subsequent recommendation of three sites for characterization as candidate sites. 428 refs., 24 figs., 62 tabs

Nevada Test Site Environmental Report 2009, Attachment A: Site Description

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills, ed.

2010-09-13

This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2009. Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site’s environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

CERCLA site assessment workbook, Volume 1

International Nuclear Information System (INIS)

1994-08-01

This workbook provides instructions for planning, implementing, and reporting site assessments under CERCLA, commonly referred to as Superfund. Site assessment consists of two information-gathering steps: the remedial preliminary assessment (PA) and the site inspection (SI). The information obtained is then used to estimate, or score, a site's relative risk to public health and the environment. The score is derived via the hazard ranking system (HRS). Although the workbook and its exercises can be adapted to group study, it is designed primarily for use by an individual

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 6

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-01-01

The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

International Nuclear Information System (INIS)

1988-01-01

The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

Site-specific design of the super collider in Texas

International Nuclear Information System (INIS)

Laughton, C.; Nelson, P.P.; Lundin, T.K.

1990-01-01

This paper outlines the scope of the Superconducting Super Collider (SSC) in Texas, underground works and present the current accelerator layout. After a brief overview of the site geotechnical characteristics, emphasis will be placed upon the possibilities for the incorporation of mechanical excavation technology into the construction of the various underground structures

Site-specific design of the super collider in Texas

International Nuclear Information System (INIS)

Laughton, C.; Nelson, P.P.; Lundin, T.K.

1990-06-01

This paper will outline the scope of the Superconducting Super Collider (SSC), underground works and present the current accelerator layout. After a brief overview of the site geotechnical characteristics, emphasis will be placed upon the possibilities for the incorporation of mechanical excavation technology into the construction of the various underground structures. 5 figs

Design guidelines for teaching about design guidelines for educational WWW-sites

NARCIS (Netherlands)

Collis, Betty; Winnips, Koos; Ottmann, Thomas; Tomek, Ivan

1998-01-01

This paper describes how the authors use a mixture of World Wide Web (WWW)-based functionalities and new didactics to teach educational technology students at the University of Twente (Netherlands) about the design of WWW-based learning environments. Topics discussed include: (1) the content of

Experiences with on-site power sources at KCB

Energy Technology Data Exchange (ETDEWEB)

Heijnen, B. M.A. [Borssele Nuclear Power Station, N.V. P.Z.E.M., Postbus 48, 4330 AA Middleburg (Netherlands)

1986-02-15

The design of the nuclear power station is of the late sixties. The experiences with the on-site power sources, signal processing and some of the resulting modifications of the design of the power plant are mentioned. In order to let the design satisfy as much as possible present ideas about safety, it was decided to realize a total new and Independent decay heat removal System. With this system a second independent on-site power System is at disposal in case of accident situations. (author)

Conceptual designs for waste packages for horizontal or vertical emplacement in a repository in salt for reference in the site characterization plan

International Nuclear Information System (INIS)

1987-06-01

This report includes the options of horizontal and vertical emplacement, the addition of a phased repository, an additional waste form (intact spent fuel), revised geotechnical data appropriate for the Deaf Smith County site, new corrosion data for the container, and new repository design data. The waste package consists of waste form and canister within a thick-walled, low-carbon steel container surrounded by packing. The container is a hollow cylinder with a flat head welded to each end. The design concepts for the waste container or vertical and horizontal emplacement are identical. This report discusses the results of analyses of aspects of the reference waste package concept needing changes because of new data and information believed applicable to the Deaf Smith County site. Included are waste package conceptual designs or (1) the reference defense high-level waste form from the Savannah River Plant; (2) intact spent fuel with our pressurized-water-reactor or nine boiling-water-reactor assemblies per package for emplacement during Phase 1 of repository operation; and (3) spent fuel which has been disassembled and consolidated into a segmented cylindrical canister with rods from either 12 pressurized-water-reactor or 30 boiling-water-reactor assemblies per package for emplacement during Phase 2. 30 refs., 61 figs., 30 tabs

Transitioning from Marketing-Oriented Design to User-Oriented Design: A Case Study

Science.gov (United States)

Laster, Shari; Stitz, Tammy; Bove, Frank J.; Wise, Casey

2011-01-01

The transition to a new architecture and design for an academic library Web site does not always proceed smoothly. In this case study, a library at a large research university hired an outside Web development contractor to create a new architecture and design for the university's Web site using dotCMS, an open-source content management system. The…

The extension of Rome׳s Capitoline Museums and the design of a new Hall on the site of the ancient ‘Giardino Romano’

Directory of Open Access Journals (Sweden)

Raffaele Panella

2015-09-01

Full Text Available The new Hall of Marcus Aurelius in the Capitoline Museums, located within the ancient site of Giardino Romano, displays the original statue of the Roman emperor of the 2nd century AD. The idea of extending the Capitoline Museums by including this site came about in the framework of its general redevelopment.11 The chronology of the design work stretches from 1993 to 2002; the works have been achieved between 2004 and 2005. The design leader was Carlo Aymonino and his collaborators architects Maria Luisa Tugnoli, Geneviève Hanssen, Raffaella Castrignanò. The structural design is by engineer Antonio Michetti, with Giuseppe Silvetti and architect Marco Astolfi. The new Hall is the result of a long and complicated process (1988–2005 considering the exceptional importance of the site and the many changes brought to the museum programme during the said period (Figures 1 and 2.In fact, the new Hall was originally supposed to display the marbles of the Temple of Apollo Sosianus, the foundation wall of the Temple of Capitoline Jupiter, embedded within the structures of the Palazzo Caffarelli, opposite the Giardino Romano. However, in 1997, the plan for the Capitoline Museum changed radically as the statue of Marcus Aurelius, which had been restored following the blast of a bomb attack in 1979, was determined to be the focus of the Hall. The project finally consisted of a steel and glass structure on an elliptic plan andshaped around the foundations of the Temple, with the statue at its center.

Hanford Site waste tank farm facilities design reconstitution program plan

International Nuclear Information System (INIS)

Vollert, F.R.

1994-01-01

Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980's has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan

The design and implementation of web mining in web sites security

Science.gov (United States)

Li, Jian; Zhang, Guo-Yin; Gu, Guo-Chang; Li, Jian-Li

2003-06-01

The backdoor or information leak of Web servers can be detected by using Web Mining techniques on some abnormal Web log and Web application log data. The security of Web servers can be enhanced and the damage of illegal access can be avoided. Firstly, the system for discovering the patterns of information leakages in CGI scripts from Web log data was proposed. Secondly, those patterns for system administrators to modify their codes and enhance their Web site security were provided. The following aspects were described: one is to combine web application log with web log to extract more information, so web data mining could be used to mine web log for discovering the information that firewall and Information Detection System cannot find. Another approach is to propose an operation module of web site to enhance Web site security. In cluster server session, Density-Based Clustering technique is used to reduce resource cost and obtain better efficiency.

Site environmental report for calendar year 1996: Yucca Mountain site, Nye County, Nevada

International Nuclear Information System (INIS)

1997-11-01

The environmental program established by the Yucca Mountain Site Characterization Office (YMSCO) has been designed and implemented to protect, maintain, and restore environmental quality, minimize potential threats to the environment and the public, and comply with environmental policies and US Department of Energy (DOE) Orders. In accordance with DOE Order 5400.1, General Environmental Protection Program (DOE, 1990a), to be superseded by DOE Order 231.1 (under review), the status of the Yucca Mountain Site Characterization Project (YMP) environmental program has been summarized in this annual Site Environmental Report (SER) to characterize performance, document compliance with environmental requirements, and highlight significant programs and efforts during calendar year 1996

Spatiotemporally Representative and Cost-Efficient Sampling Design for Validation Activities in Wanglang Experimental Site

Directory of Open Access Journals (Sweden)

Gaofei Yin

2017-11-01

Full Text Available Spatiotemporally representative Elementary Sampling Units (ESUs are required for capturing the temporal variations in surface spatial heterogeneity through field measurements. Since inaccessibility often coexists with heterogeneity, a cost-efficient sampling design is mandatory. We proposed a sampling strategy to generate spatiotemporally representative and cost-efficient ESUs based on the conditioned Latin hypercube sampling scheme. The proposed strategy was constrained by multi-temporal Normalized Difference Vegetation Index (NDVI imagery, and the ESUs were limited within a sampling feasible region established based on accessibility criteria. A novel criterion based on the Overlapping Area (OA between the NDVI frequency distribution histogram from the sampled ESUs and that from the entire study area was used to assess the sampling efficiency. A case study in Wanglang National Nature Reserve in China showed that the proposed strategy improves the spatiotemporally representativeness of sampling (mean annual OA = 74.7% compared to the single-temporally constrained (OA = 68.7% and the random sampling (OA = 63.1% strategies. The introduction of the feasible region constraint significantly reduces in-situ labour-intensive characterization necessities at expenses of about 9% loss in the spatiotemporal representativeness of the sampling. Our study will support the validation activities in Wanglang experimental site providing a benchmark for locating the nodes of automatic observation systems (e.g., LAINet which need a spatially distributed and temporally fixed sampling design.

Electrical Ground System Design of PEFP

International Nuclear Information System (INIS)

Mun, Kyeong Jun; Jeon, Gye Po; Park, Sung Sik; Min, Yi Sub; Nam, Jung Min; Cho, Jang Hyung; Kim, Jun Yeon

2010-01-01

Since host site host site was selected Gyeong-ju city in January, 2006. we need design revision of Proton Accelerator research center to reflect on host site characteristics and several conditions. In this paper, electrical grounding and lightning protection design scheme is introduced. In electrical grounding system design of PEFP, we classified electrical facilities into 4 groups; equipment grounding (type A), instrument grounding (Type A), high frequency instrument grounding (Type C) and lightning arrestor grounding (Type D). Lightning protection system is designed in all buildings of proton accelerator research center of PEFP, including switchyard

Electrical Ground System Design of PEFP

Energy Technology Data Exchange (ETDEWEB)

Mun, Kyeong Jun; Jeon, Gye Po; Park, Sung Sik; Min, Yi Sub; Nam, Jung Min; Cho, Jang Hyung; Kim, Jun Yeon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-10-15

Since host site host site was selected Gyeong-ju city in January, 2006. we need design revision of Proton Accelerator research center to reflect on host site characteristics and several conditions. In this paper, electrical grounding and lightning protection design scheme is introduced. In electrical grounding system design of PEFP, we classified electrical facilities into 4 groups; equipment grounding (type A), instrument grounding (Type A), high frequency instrument grounding (Type C) and lightning arrestor grounding (Type D). Lightning protection system is designed in all buildings of proton accelerator research center of PEFP, including switchyard