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Sample records for determines akt1 nuclear

  1. Complex formation of p65/RelA with nuclear Akt1 for enhanced transcriptional activation of NF-κB

    International Nuclear Information System (INIS)

    Kwon, Osong; Kim, Kyung A; He, Long; Jung, Mira; Jeong, Sook Jung; Ahn, Jong Seog; Kim, Bo Yeon

    2008-01-01

    Akt1 was revealed to interact with Ki-Ras in the cytoplasm of Ki-Ras-transformed human prostate epithelial cells, 267B1/K-ras. Moreover, p65/RelA in the nucleus was found to interact with both Ki-Ras and Akt1, suggesting the nuclear translocation of Akt1:Ki-Ras complex for NF- κB activation. In support of this, compared with wild type Akt1, the dominant negative Akt1 mutant was decreased in its nuclear expression, reducing the Ki-Ras-induced NF-κB transcriptional activation. Moreover, inhibitors of Ras (sulindac sulfide and farnesyltransferase inhibitor I) or PI3K/Akt (wortmannin), reduced the amounts of Akt1 and Ki-Ras in the nucleus as well as partial NF-κB activity. The complete inhibition of Ki-Ras-induced NF-κB activation, however, could only be obtained by combined treatment with wortmannin and proteasome inhibitor-1. Accordingly, clonogenic assay showed Akt1 contribution to IκBα-mediated NF-κB activation for oncogenic cell growth by Ki-Ras. Our data suggest a crucial role of Ki-Ras:Akt1 complex in NF-κB transcriptional activation and enhancement of cell survival

  2. Akt1 intramitochondrial cycling is a crucial step in the redox modulation of cell cycle progression.

    Directory of Open Access Journals (Sweden)

    Valeria Gabriela Antico Arciuch

    2009-10-01

    Full Text Available Akt is a serine/threonine kinase involved in cell proliferation, apoptosis, and glucose metabolism. Akt is differentially activated by growth factors and oxidative stress by sequential phosphorylation of Ser(473 by mTORC2 and Thr(308 by PDK1. On these bases, we investigated the mechanistic connection of H(2O(2 yield, mitochondrial activation of Akt1 and cell cycle progression in NIH/3T3 cell line with confocal microscopy, in vivo imaging, and directed mutagenesis. We demonstrate that modulation by H(2O(2 entails the entrance of cytosolic P-Akt1 Ser(473 to mitochondria, where it is further phosphorylated at Thr(308 by constitutive PDK1. Phosphorylation of Thr(308 in mitochondria determines Akt1 passage to nuclei and triggers genomic post-translational mechanisms for cell proliferation. At high H(2O(2, Akt1-PDK1 association is disrupted and P-Akt1 Ser(473 accumulates in mitochondria in detriment to nuclear translocation; accordingly, Akt1 T308A is retained in mitochondria. Low Akt1 activity increases cytochrome c release to cytosol leading to apoptosis. As assessed by mass spectra, differential H(2O(2 effects on Akt1-PDK interaction depend on the selective oxidation of Cys(310 to sulfenic or cysteic acids. These results indicate that Akt1 intramitochondrial-cycling is central for redox modulation of cell fate.

  3. AKT Inhibition in Solid Tumors With AKT1 Mutations.

    Science.gov (United States)

    Hyman, David M; Smyth, Lillian M; Donoghue, Mark T A; Westin, Shannon N; Bedard, Philippe L; Dean, Emma J; Bando, Hideaki; El-Khoueiry, Anthony B; Pérez-Fidalgo, José A; Mita, Alain; Schellens, Jan H M; Chang, Matthew T; Reichel, Jonathan B; Bouvier, Nancy; Selcuklu, S Duygu; Soumerai, Tara E; Torrisi, Jean; Erinjeri, Joseph P; Ambrose, Helen; Barrett, J Carl; Dougherty, Brian; Foxley, Andrew; Lindemann, Justin P O; McEwen, Robert; Pass, Martin; Schiavon, Gaia; Berger, Michael F; Chandarlapaty, Sarat; Solit, David B; Banerji, Udai; Baselga, José; Taylor, Barry S

    2017-07-10

    Purpose AKT1 E17K mutations are oncogenic and occur in many cancers at a low prevalence. We performed a multihistology basket study of AZD5363, an ATP-competitive pan-AKT kinase inhibitor, to determine the preliminary activity of AKT inhibition in AKT-mutant cancers. Patients and Methods Fifty-eight patients with advanced solid tumors were treated. The primary end point was safety; secondary end points were progression-free survival (PFS) and response according to Response Evaluation Criteria in Solid Tumors (RECIST). Tumor biopsies and plasma cell-free DNA (cfDNA) were collected in the majority of patients to identify predictive biomarkers of response. Results In patients with AKT1 E17K-mutant tumors (n = 52) and a median of five lines of prior therapy, the median PFS was 5.5 months (95% CI, 2.9 to 6.9 months), 6.6 months (95% CI, 1.5 to 8.3 months), and 4.2 months (95% CI, 2.1 to 12.8 months) in patients with estrogen receptor-positive breast, gynecologic, and other solid tumors, respectively. In an exploratory biomarker analysis, imbalance of the AKT1 E17K-mutant allele, most frequently caused by copy-neutral loss-of-heterozygosity targeting the wild-type allele, was associated with longer PFS (hazard ratio [HR], 0.41; P = .04), as was the presence of coincident PI3K pathway hotspot mutations (HR, 0.21; P = .045). Persistent declines in AKT1 E17K in cfDNA were associated with improved PFS (HR, 0.18; P = .004) and response ( P = .025). Responses were not restricted to patients with detectable AKT1 E17K in pretreatment cfDNA. The most common grade ≥ 3 adverse events were hyperglycemia (24%), diarrhea (17%), and rash (15.5%). Conclusion This study provides the first clinical data that AKT1 E17K is a therapeutic target in human cancer. The genomic context of the AKT1 E17K mutation further conditioned response to AZD5363.

  4. Akt1 deficiency diminishes skeletal muscle hypertrophy by reducing satellite cell proliferation.

    Science.gov (United States)

    Moriya, Nobuki; Miyazaki, Mitsunori

    2018-02-14

    Skeletal muscle mass is determined by the net dynamic balance between protein synthesis and degradation. Although the Akt/mechanistic target of rapamycin (mTOR)-dependent pathway plays an important role in promoting protein synthesis and subsequent skeletal muscle hypertrophy, the precise molecular regulation of mTOR activity by the upstream protein kinase Akt is largely unknown. In addition, the activation of satellite cells has been indicated as a key regulator of muscle mass. However, the requirement of satellite cells for load-induced skeletal muscle hypertrophy is still under intense debate. In this study, female germline Akt1 knockout (KO) mice were used to examine whether Akt1 deficiency attenuates load-induced skeletal muscle hypertrophy through suppressing mTOR-dependent signaling and satellite cell proliferation. Akt1 KO mice showed a blunted hypertrophic response of skeletal muscle, with a diminished rate of satellite cell proliferation following mechanical overload. In contrast, Akt1 deficiency did not affect the load-induced activation of mTOR signaling and the subsequent enhanced rate of protein synthesis in skeletal muscle. These observations suggest that the load-induced activation of mTOR signaling occurs independently of Akt1 regulation and that Akt1 plays a critical role in regulating satellite cell proliferation during load-induced muscle hypertrophy.

  5. Akt1 binds focal adhesion kinase via the Akt1 kinase domain independently of the pleckstrin homology domain.

    Science.gov (United States)

    Basson, M D; Zeng, B; Wang, S

    2015-10-01

    Akt1 and focal adhesion kinase (FAK) are protein kinases that play key roles in normal cell signaling. Individually, aberrant expression of these kinases has been linked to a variety of cancers. Together, Akt1/FAK interactions facilitate cancer metastasis by increasing cell adhesion under conditions of increased extracellular pressure. Pathological and iatrogenic sources of pressure arise from tumor growth against constraining stroma or direct perioperative manipulation. We previously reported that 15 mmHg increased extracellular pressure causes Akt1 to both directly interact with FAK and to phosphorylate and activate it. We investigated the nature of the Akt1/FAK binding by creating truncations of recombinant FAK, conjugated to glutathione S-transferase (GST), to pull down full-length Akt1. Western blots probing for Akt1 showed that FAK/Akt1 binding persisted in FAK truncations consisting of only amino acids 1-126, FAK(NT1), which contains the F1 subdomain of its band 4.1, ezrin, radixin, and moesin (FERM) domain. Using FAK(NT1) as bait, we then pulled down truncated versions of recombinant Akt1 conjugated to HA (human influenza hemagglutinin). Probes for GST-FAK(NT1) showed Akt1-FAK binding to occur in the absence of the both the Akt1 (N)-terminal pleckstrin homology (PH) domain and its adjacent hinge region. The Akt1 (C)-terminal regulatory domain was equally unnecessary for Akt1/FAK co-immunoprecipitation. Truncations involving the Akt1 catalytic domain showed that the domain by itself was enough to pull down FAK. Additionally, a fragment spanning from the PH domain to half way through the catalytic domain demonstrated increased FAK binding compared to full length Akt1. These results begin to delineate the Akt1/FAK interaction and can be used to manipulate their force-activated signal interactions. Furthermore, the finding that the N-terminal half of the Akt1 catalytic domain binds so strongly to FAK when cleaved from the rest of the protein may suggest a means

  6. Cytoplasmic Skp2 expression is associated with p-Akt1 and predicts poor prognosis in human breast carcinomas.

    Directory of Open Access Journals (Sweden)

    Jing Liu

    Full Text Available BACKGROUND: S-phase kinase protein 2 (Skp2, an oncogenic protein, is a key regulator in different cellular and molecular processes, through ubiquitin-proteasome degradation pathway. Increased levels of Skp2 are observed in various types of cancer and associated with poor prognosis. However, in human breast carcinomas, the underlying mechanism and prognostic significance of cytoplasmic Skp2 is still undefined. METHODS: To investigate the role of cytoplasmic Skp2 expression in human breast carcinomas, we immnohistochemically assessed cytoplasmic Skp2, p-Akt1, and p27 expression in 251 patients with invasive ductal carcinomas of the breast. Association of cytoplasmic Skp2 expression with p-Akt1 and p27 was analyzed as well as correspondence with other clinicopathological parameters. Disease-free survival and overall survival were determined based on the Kaplan-Meier method and Cox regression models. RESULTS: Cytoplasmic of Skp2 was detected in 165 out of 251 (65.7% patients. Cytoplasmic Skp2 expression was associated with larger tumor size, more advanced histological grade, and positive HER2 expression. Increased cytoplasmic Skp2 expression correlated with p-Akt1 expression, with 54.2% (51/94 of low p-Akt1-expressing breast carcinomas, but 72.6% (114/157 of high p-Akt1-expressing breast carcinomas exhibiting cytoplasmic Skp2 expression. Elevated cytoplasmic Skp2 expression with low p-Akt1 expression was associated with poor disease-free and overall survival (DFS and OS, and Cox regression models demonstrated that cytoplasmic Skp2 expression was an independent prognostic marker for invasive breast carcinomas. CONCLUSION: Cytoplasmic Skp2 expression is associated with aggressive prognostic factors, such as larger tumor size, and advanced histological grade of the breast cancers. Results demonstrate that combined cytoplasmic Skp2 and p-Akt1 expression may be prognostic for patients with invasive breast carcinomas, and cytoplasmic Skp2 may serve as a

  7. Loss of Akt1 in mice increases energy expenditure and protects against diet-induced obesity.

    Science.gov (United States)

    Wan, Min; Easton, Rachael M; Gleason, Catherine E; Monks, Bobby R; Ueki, Kohjiro; Kahn, C Ronald; Birnbaum, Morris J

    2012-01-01

    Akt is encoded by a gene family for which each isoform serves distinct but overlapping functions. Based on the phenotypes of the germ line gene disruptions, Akt1 has been associated with control of growth, whereas Akt2 has been linked to metabolic regulation. Here we show that Akt1 serves an unexpected role in the regulation of energy metabolism, as mice deficient for Akt1 exhibit protection from diet-induced obesity and its associated insulin resistance. Although skeletal muscle contributes most of the resting and exercising energy expenditure, muscle-specific deletion of Akt1 does not recapitulate the phenotype, indicating that the role of Akt1 in skeletal muscle is cell nonautonomous. These data indicate a previously unknown function of Akt1 in energy metabolism and provide a novel target for treatment of obesity.

  8. Subcriticality determination of nuclear reactor

    International Nuclear Information System (INIS)

    Borisenko, V.I.; Goranchuk, V.V.; Sidoruk, N.M.; Volokh, A.F.

    2014-01-01

    In this article the subcriticality determination of nuclear reactor is considered. Emphasized that, despite the requirements of regulatory documents on the subcriticality determination of WWER from the beginning of their operation, so far, this problem has not been solved. The results of subcriticality determination of Rossi-α method of the WWER-M is presented. The possibility of subcriticality determination of WWER is considered. The possibility of subcriticality determination of Rossi-α method with time resolution is of about 100 microseconds is also considered. The possible reasons for the error in subcriticality determination of the reactor are indicated

  9. Protein kinase B/Akt1 inhibits autophagy by down-regulating UVRAG expression

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Wonseok; Ju, Ji-hyun; Lee, Kyung-min; Nam, KeeSoo; Oh, Sunhwa [Department of Life Science, College of Natural Science, Hanyang University, 17 Haengdang-dong, Seongdong-gu, Seoul 133-791 (Korea, Republic of); Shin, Incheol, E-mail: incheol@hanyang.ac.kr [Department of Life Science, College of Natural Science, Hanyang University, 17 Haengdang-dong, Seongdong-gu, Seoul 133-791 (Korea, Republic of)

    2013-02-01

    Autophagy, or autophagocytosis, is a selective intracellular degradative process involving the cell's own lysosomal apparatus. An essential component in cell development, homeostasis, repair and resistance to stress, autophagy may result in either cell death or survival. The targeted region of the cell is sequestered within a membrane structure, the autophagosome, for regulation of the catabolic process. A key factor in both autophagosome formation and autophagosome maturation is a protein encoded by the ultraviolet irradiation resistance-associated gene (UVRAG). Conversely, the serine/threonine-specific protein kinase B (PKB, also known as Akt), which regulates survival in various cancers, inhibits autophagy through mTOR activation. We found that Akt1 may also directly inhibit autophagy by down-regulating UVRAG both in a 293T transient transfection system and breast cancer cells stably expressing Akt1. The UVRAG with mutations at putative Akt1-phosphorylation sites were still inhibited by Akt1, and dominant-negative Akt1 also inhibited UVRAG expression, suggesting that Akt1 down-regulates UVRAG by a kinase activity-independent mechanism. We showed that Akt1 overexpression in MDA-MB-231 breast cancer cells down-regulated UVRAG transcription. Cells over-expressing Akt1 were more resistant than control cells to ultraviolet light-induced autophagy and exhibited the associated reduction in cell viability. Levels of the autophagosome indicator protein LC3B-II and mRFP-GFP-LC3 were reduced in cells that over-expressing Akt1. Inhibiting Akt1 by siRNA or reintroducing UVRAG gene rescued the level of LC3B-II in UV-irradiation. Altogether, these data suggest that Akt1 may inhibit autophagy by decreasing UVRAG expression, which also sensitizes cancer cells to UV irradiation.

  10. Akt1/protein kinase Bα is critical for ischemic and VEGF-mediated angiogenesis

    Science.gov (United States)

    Ackah, Eric; Yu, Jun; Zoellner, Stefan; Iwakiri, Yasuko; Skurk, Carsten; Shibata, Rei; Ouchi, Noriyuki; Easton, Rachael M.; Galasso, Gennaro; Birnbaum, Morris J.; Walsh, Kenneth; Sessa, William C.

    2005-01-01

    Akt, or protein kinase B, is a multifunctional serine-threonine protein kinase implicated in a diverse range of cellular functions including cell metabolism, survival, migration, and gene expression. However, the in vivo roles and effectors of individual Akt isoforms in signaling are not explicitly clear. Here we show that the genetic loss of Akt1, but not Akt2, in mice results in defective ischemia and VEGF-induced angiogenesis as well as severe peripheral vascular disease. Akt1 knockout (Akt1–/–) mice also have reduced endothelial progenitor cell (EPC) mobilization in response to ischemia, and reintroduction of WT EPCs, but not EPCs isolated from Akt1–/– mice, into WT mice improves limb blood flow after ischemia. Mechanistically, the loss of Akt1 reduces the basal phosphorylation of several Akt substrates, the migration of fibroblasts and ECs, and NO release. Reconstitution of Akt1–/– ECs with Akt1 rescues the defects in substrate phosphorylation, cell migration, and NO release. Thus, the Akt1 isoform exerts an essential role in blood flow control, cellular migration, and NO synthesis during postnatal angiogenesis. PMID:16075056

  11. Marked reduction of AKT1 expression and deregulation of AKT1-associated pathways in peripheral blood mononuclear cells of schizophrenia patients.

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    Nico J M van Beveren

    Full Text Available BACKGROUND: Recent studies have suggested that deregulated AKT1 signaling is associated with schizophrenia. We hypothesized that if this is indeed the case, we should observe both decreased AKT1 expression as well as deregulation of AKT1 regulated pathways in Peripheral Blood Mononuclear Cells (PBMCs of schizophrenia patients. OBJECTIVES: To examine PBMC expression levels of AKT1 in schizophrenia patients versus controls, and to examine whether functional biological processes in which AKT1 plays an important role are deregulated in schizophrenia patients. METHODS/RESULTS: A case-control study, investigating whole-genome PBMC gene expression in male, recent onset (<5 years schizophrenia patients (N = 41 as compared to controls (N = 29. Genes, differentially expressed between patients and controls were identified using ANOVA with Benjamini-Hochberg correction (false discovery rate (FDR = 0.05. Functional aspects of the deregulated set of genes were investigated with the Ingenuity Pathway Analysis (IPA Software Tool. We found significantly decreased PBMC expression of AKT1 (p<0.001, t = -4.25 in the patients. AKT1 expression was decreased in antipsychotic-free or -naive patients (N = 11, in florid psychotic (N = 20 and in remitted (N = 21 patients. A total of 1224 genes were differentially expressed between patients and controls (FDR = 0.05. Functional analysis of the entire deregulated gene set indicated deregulated canonical pathways involved in a large number of cellular processes: immune system, cell adhesion and neuronal guidance, neurotrophins and (neural growth factors, oxidative stress and glucose metabolism, and apoptosis and cell-cycle regulation. Many of these processes are associated with AKT1. CONCLUSIONS: We show significantly decreased PBMC gene expression of AKT1 in male, recent-onset schizophrenia patients. Our observations suggest that decreased PBMC AKT1 expression is a stable trait in recent onset

  12. Akt1/PKB upregulation leads to vascular smooth muscle cell hypertrophy and polyploidization

    Science.gov (United States)

    Hixon, Mary L.; Muro-Cacho, Carlos; Wagner, Mark W.; Obejero-Paz, Carlos; Millie, Elise; Fujio, Yasushi; Kureishi, Yasuko; Hassold, Terry; Walsh, Kenneth; Gualberto, Antonio

    2000-01-01

    Vascular smooth muscle cells (VSMCs) at capacitance arteries of hypertensive individuals and animals undergo marked age- and blood pressure–dependent polyploidization and hypertrophy. We show here that VSMCs at capacitance arteries of rat models of hypertension display high levels of Akt1/PKB protein and activity. Gene transfer of Akt1 to VSMCs isolated from a normotensive rat strain was sufficient to abrogate the activity of the mitotic spindle cell–cycle checkpoint, promoting polyploidization and hypertrophy. Furthermore, the hypertrophic agent angiotensin II induced VSMC polyploidization in an Akt1-dependent manner. These results demonstrate that Akt1 regulates ploidy levels in VSMCs and contributes to vascular smooth muscle polyploidization and hypertrophy during hypertension. PMID:11032861

  13. Overexpression of Akt1 enhances adipogenesis and leads to lipoma formation in zebrafish.

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    Che-Yu Chu

    Full Text Available BACKGROUND: Obesity is a complex, multifactorial disorder influenced by the interaction of genetic, epigenetic, and environmental factors. Obesity increases the risk of contracting many chronic diseases or metabolic syndrome. Researchers have established several mammalian models of obesity to study its underlying mechanism. However, a lower vertebrate model for conveniently performing drug screening against obesity remains elusive. The specific aim of this study was to create a zebrafish obesity model by over expressing the insulin signaling hub of the Akt1 gene. METHODOLOGY/PRINCIPAL FINDINGS: Skin oncogenic transformation screening shows that a stable zebrafish transgenic of Tg(krt4Hsa.myrAkt1(cy18 displays severely obese phenotypes at the adult stage. In Tg(krt4:Hsa.myrAkt1(cy18, the expression of exogenous human constitutively active Akt1 (myrAkt1 can activate endogenous downstream targets of mTOR, GSK-3α/β, and 70S6K. During the embryonic to larval transitory phase, the specific over expression of myrAkt1 in skin can promote hypertrophic and hyperplastic growth. From 21 hour post-fertilization (hpf onwards, myrAkt1 transgene was ectopically expressed in several mesenchymal derived tissues. This may be the result of the integration position effect. Tg(krt4:Hsa.myrAkt1(cy18 caused a rapid increase of body weight, hyperplastic growth of adipocytes, abnormal accumulation of fat tissues, and blood glucose intolerance at the adult stage. Real-time RT-PCR analysis showed the majority of key genes on regulating adipogenesis, adipocytokine, and inflammation are highly upregulated in Tg(krt4:Hsa.myrAkt1(cy18. In contrast, the myogenesis- and skeletogenesis-related gene transcripts are significantly downregulated in Tg(krt4:Hsa.myrAkt1(cy18, suggesting that excess adipocyte differentiation occurs at the expense of other mesenchymal derived tissues. CONCLUSION/SIGNIFICANCE: Collectively, the findings of this study provide direct evidence that Akt1

  14. Akt1 Controls the Timing and Amplitude of Vascular Circadian Gene Expression

    OpenAIRE

    Luciano, Amelia K.; Santana, Jeans M.; Velazquez, Heino; Sessa, William C.

    2017-01-01

    The AKT signaling pathway is important for circadian rhythms in mammals and flies (Drosophila). However, AKT signaling in mammals is more complicated since there are 3 isoforms of AKT, each performing slightly different functions. Here we study the most ubiquitous AKT isoform, Akt1, and its role at the organismal level in the central and vascular peripheral clocks. Akt1−/− mice exhibit relatively normal behavioral rhythms with only minor differences in circadian gene expression in the liver a...

  15. Akt1/PKB upregulation leads to vascular smooth muscle cell hypertrophy and polyploidization

    OpenAIRE

    Hixon, Mary L.; Muro-Cacho, Carlos; Wagner, Mark W.; Obejero-Paz, Carlos; Millie, Elise; Fujio, Yasushi; Kureishi, Yasuko; Hassold, Terry; Walsh, Kenneth; Gualberto, Antonio

    2000-01-01

    Vascular smooth muscle cells (VSMCs) at capacitance arteries of hypertensive individuals and animals undergo marked age- and blood pressure–dependent polyploidization and hypertrophy. We show here that VSMCs at capacitance arteries of rat models of hypertension display high levels of Akt1/PKB protein and activity. Gene transfer of Akt1 to VSMCs isolated from a normotensive rat strain was sufficient to abrogate the activity of the mitotic spindle cell–cycle checkpoint, promoting polyploidizati...

  16. AKT1 loss correlates with episomal HPV16 in vulval intraepithelial neoplasia.

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    Arucha L Ekeowa-Anderson

    Full Text Available Anogenital malignancy has a significant association with high-risk mucosal alpha-human papillomaviruses (alpha-PV, particularly HPV 16 and 18 whereas extragenital SCC has been linked to the presence of cutaneous beta and gamma-HPV types. Vulval skin may be colonised by both mucosal and cutaneous (beta-, mu-, nu- and gamma- PV types, but there are few systematic studies investigating their presence and their relative contributions to vulval malignancy. Dysregulation of AKT, a serine/threonine kinase, plays a significant role in several cancers. Mucosal HPV types can increase AKT phosphorylation and activity whereas cutaneous HPV types down-regulate AKT1 expression, probably to weaken the cornified envelope to promote viral release. We assessed the presence of mucosal and cutaneous HPV in vulval malignancy and its relationship to AKT1 expression in order to establish the corresponding HPV and AKT1 profile of normal vulval skin, vulval intraepithelial neoplasia (VIN and vulval squamous cell carcinoma (vSCC. We show that HPV16 is the principle HPV type present in VIN, there were few detectable beta types present and AKT1 loss was not associated with the presence of these cutaneous HPV. We show that HPV16 early gene expression reduced AKT1 expression in transgenic mouse epidermis. AKT1 loss in our VIN cohort correlated with presence of high copy number, episomal HPV16. Maintained AKT1 expression correlated with low copy number, an increased frequency of integration and increased HPV16E7 expression, a finding we replicated in another untyped cohort of vSCC. Since expression of E7 reflects tumour progression, these findings suggest that AKT1 loss associated with episomal HPV16 may have positive prognostic implications in vulval malignancy.

  17. Akt1/protein kinase Bα is critical for ischemic and VEGF-mediated angiogenesis

    OpenAIRE

    Ackah, Eric; Yu, Jun; Zoellner, Stefan; Iwakiri, Yasuko; Skurk, Carsten; Shibata, Rei; Ouchi, Noriyuki; Easton, Rachael M.; Galasso, Gennaro; Birnbaum, Morris J.; Walsh, Kenneth; Sessa, William C.

    2005-01-01

    Akt, or protein kinase B, is a multifunctional serine-threonine protein kinase implicated in a diverse range of cellular functions including cell metabolism, survival, migration, and gene expression. However, the in vivo roles and effectors of individual Akt isoforms in signaling are not explicitly clear. Here we show that the genetic loss of Akt1, but not Akt2, in mice results in defective ischemia and VEGF-induced angiogenesis as well as severe peripheral vascular disease. Akt1 knockout (Ak...

  18. Mechanism of Akt1 inhibition of breast cancer cell invasionreveals a protumorigenic role for TSC2

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Hong; Radisky, Derek C.; Nelson, Celeste M.; Zhang, Hui; Fata, Jimmie; Roth, Richard A.; Bissell, Mina J.

    2006-02-07

    Akt1 is frequently upregulated in human tumors, and has been shown to accelerate cell proliferation and to suppress programmed cell death; consequently, inhibiting the activity of Akt1 has been seen as an attractive target for therapeutic intervention. Paradoxically, hyperactivation of the Akt1 oncogene can also prevent the invasive behavior that underlies progression to metastasis. Here we show that overexpression of activated myr-Akt1 in human breast cancer cells phosphorylates and thereby targets the tumor suppressor tuberous sclerosis complex 2 (TSC2) for degradation, leading to reduced Rho-GTPase activity, decreased actin stress fibers and focal adhesions, and reduced motility and invasion. Overexpression of TSC2 rescues the migration phenotype of myr-Akt1-expressing tumor cells, and high levels of TSC2 in breast cancer patients correlate with increased metastasis and reduced survival. These data indicate that the functional properties of genes designated as oncogenes or tumor suppressor genes depends on the context of the cell type and the tissues studied, and suggest the need for caution in designing therapies targeting the function of individual genes in epithelial tissues.

  19. AKT1 moderation of cannabis-induced cognitive alterations in psychotic disorder.

    Science.gov (United States)

    van Winkel, Ruud; van Beveren, Nico J M; Simons, Claudia

    2011-11-01

    Genetic variation in AKT1 may be associated with sensitivity to the psychotomimetic effects of cannabis as well as with increased risk for psychotic disorder following cannabis use. Investigation of the effect of this interaction on relevant intermediate phenotypes for psychosis, such as cognition, may help to clarify the underlying mechanism. Thus, verbal memory (visually presented Word Learning Task), sustained attention (Continuous Performance Test, CPT), AKT1 rs2494732 genotype, and cannabis use were examined in a large cohort of patients with psychotic disorder. No evidence was found for AKT1 × cannabis interaction on verbal memory. Cannabis use preceding onset of psychotic disorder did interact significantly with AKT1 rs2494732 genotype to affect CPT reaction time (β=8.0, SE 3.9, p=0.037) and CPT accuracy (β=-1.2, SE 0.4, p=0.003). Cannabis-using patients with the a priori vulnerability C/C genotype were slower and less accurate on the CPT, whereas cannabis-using patients with the T/T genotype had similar or better performance than non-using patients with psychotic disorder. The interaction was also apparent in patients with psychotic disorder who had not used cannabis in the 12 months preceding assessment, but was absent in the unaffected siblings of these patients and in healthy controls. In conclusion, cannabis use before onset of psychosis may have long-lasting effects on measures of sustained attention, even in the absence of current use, contingent on AKT1 rs2494732 genotype. The results suggest that long-term changes in cognition may mediate the risk-increasing effect of the AKT1 × cannabis interaction on psychotic disorder.

  20. Effect of Agmatine Sulfate on Modulation of Matrix Metalloproteinases via PI3K/Akt-1 in HT1080 Cells.

    Science.gov (United States)

    Kim, Hyejeong; Kim, Moon-Moo

    2017-11-01

    The purpose of this study was to investigate the mechanism by which agmatine sulfate induces an anti-metastatic effect in human HT1080 fibrosarcoma cells, by affecting matrix metalloproteinases (MMPs). For the experiments, we used a non-toxic concentration of agmatine, below 512 μM, that was determined using an MTT assay. The effect of agmatine sulfate on metastasis was gelatin zymography, western blot, immunofluorescence staining and cell invasion assay. Agmatine sulfate inhibited MMP-2 activity stimulated by phenazine methosulfate (PMS). Furthermore, the expression level of MMP-2 stimulated by PMS, was decreased, but the expression level of TIMP-1 was increased in the presence of agmatine sulfate. Moreover, it was observed that the expression levels of ERK and p38 were increased, but those of PI3K and Akt-1 associated with the modulation of MMP-2 were decreased in this study. Furthermore, agmatine sulfate decreased the invasion level of human fibrosarcoma cells stimulated by VEGF. These results suggest that agmatine sulfate could inhibit metastasis through inhibition of MMP-2 via the PI3K/Akt-1 signaling pathway. Copyright© 2017, International Institute of Anticancer Research (Dr. George J. Delinasios), All rights reserved.

  1. Akt1 is essential for postnatal mammary gland development, function, and the expression of Btn1a1.

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    Jessica LaRocca

    Full Text Available Akt1, a serine-threonine protein kinase member of the PKB/Akt gene family, plays critical roles in the regulation of multiple cellular processes, and has previously been implicated in lactation and breast cancer development. In this study, we utilized Akt1+/+ and Akt1-/- C57/Bl6 female mice to assess the role that Akt1 plays in normal mammary gland postnatal development and function. We examined postnatal morphology at multiple time points, and analyzed gene and protein expression changes that persist into adulthood. Akt1 deficiency resulted in several mammary gland developmental defects, including ductal outgrowth and defective terminal end bud formation. Adult Akt1-/- mammary gland composition remained altered, exhibiting fewer alveolar buds coupled with increased epithelial cell apoptosis. Microarray analysis revealed that Akt1 deficiency altered expression of genes involved in numerous biological processes in the mammary gland, including organismal development, cell death, and tissue morphology. Of particular importance, a significant decrease in expression of Btn1a1, a gene involved in milk lipid secretion, was observed in Akt1-/- mammary glands. Additionally, pseudopregnant Akt1-/- females failed to induce Btn1a1 expression in response to hormonal stimulation compared to their wild-type counterparts. Retroviral-mediated shRNA knockdown of Akt1 and Btn1a1 in MCF-7 human breast epithelial further illustrated the importance of Akt1 in mammary epithelial cell proliferation, as well as in the regulation of Btn1a1 and subsequent expression of ß-casein, a gene that encodes for milk protein. Overall these findings provide mechanistic insight into the role of Akt1 in mammary morphogenesis and function.

  2. AKT1 fails to replicate as a longevity-associated gene in Danish and German nonagenarians and centenarians

    DEFF Research Database (Denmark)

    Nygaard, Marianne; Soerensen, Mette; Flachsbart, Friederike

    2013-01-01

    In addition to APOE and FOXO3, AKT1 has recently been suggested as a third consistent longevity gene, with variants in AKT1 found to be associated with human lifespan in two previous studies. Here, we evaluated AKT1 as a longevity-associated gene across populations by attempting to replicate the ...... not support AKT1 as a universal longevity-associated gene.European Journal of Human Genetics advance online publication, 29 August 2012; doi:10.1038/ejhg.2012.196....

  3. AKT1 Moderation of Cannabis-Induced Cognitive Alterations in Psychotic Disorder

    NARCIS (Netherlands)

    van Winkel, R.; van Beveren, N.J.; Simons, C.; Kahn, R.S.; Linszen, D.H.; van Os, J.; Wiersma, D.; Bruggeman, R.; Cahn, W.; de Haan, L.; Krabbendam, L.; Myin-Germeys, I.

    2011-01-01

    Genetic variation in AKT1 may be associated with sensitivity to the psychotomimetic effects of cannabis as well as with increased risk for psychotic disorder following cannabis use. Investigation of the effect of this interaction on relevant intermediate phenotypes for psychosis, such as cognition,

  4. AKT1 moderation of cannabis-induced cognitive alterations in psychotic disorder

    NARCIS (Netherlands)

    van Winkel, Ruud; van Beveren, Nico J. M.; Simons, Claudia; Kahn, René S.; Linszen, Don H.; van Os, Jim; Wiersma, Durk; Bruggeman, Richard; Cahn, Wiepke; de Haan, Lieuwe; Krabbendam, Lydia; Myin-Germeys, Inez

    2011-01-01

    Genetic variation in AKT1 may be associated with sensitivity to the psychotomimetic effects of cannabis as well as with increased risk for psychotic disorder following cannabis use. Investigation of the effect of this interaction on relevant intermediate phenotypes for psychosis, such as cognition,

  5. Cannabis and a lower BMI in psychosis : What is the role of AKT1?

    NARCIS (Netherlands)

    Liemburg, Edith J.; Bruins, Jojanneke; van Beveren, Nico; Islam, Atiqul; Alizadeh, Behrooz Z.

    2016-01-01

    Cannabis use has been associated with favorable outcomes on metabolic risk factors. The cause of this relation is still unknown. In this study we investigated whether this effect is mediated by the AKT1 gene, as activation of the related enzyme by cannabis may cause metabolic changes. Six Single

  6. UV light induces premature senescence in Akt1-null mouse embryonic fibroblasts by increasing intracellular levels of ROS

    International Nuclear Information System (INIS)

    Jee, Hye Jin; Kim, Hyun-Ju; Kim, Ae Jeong; Bae, Yoe-Sik; Bae, Sun Sik; Yun, Jeanho

    2009-01-01

    Akt/PKB plays a pivotal role in cell survival and proliferation. Previously, we reported that UV-irradiation induces extensive cell death in Akt2 -/- mouse embryonic fibroblasts (MEFs) while Akt1 -/- MEFs show cell cycle arrest. Here, we find that Akt1 -/- MEFs exhibit phenotypic changes characteristics of senescence upon UV-irradiation. An enlarged and flattened morphology, a reduced cell proliferation and an increased senescence-associated β-galactosidase (SA β-gal) staining indicate that Akt1 -/- MEFs undergo premature senescence after UV-irradiation. Restoring Akt1 expression in Akt1 -/- MEFs suppressed SA β-gal activity, indicating that UV-induced senescence is due to the absence of Akt1 function. Notably, levels of ROS were rapidly increased upon UV-irradiation and the ROS scavenger NAC inhibits UV-induced senescence of Akt1 -/- MEFs, suggesting that UV light induces premature senescence in Akt1 -/- MEFs by modulating intracellular levels of ROS. In conjunction with our previous work, this indicates that different isoforms of Akt have distinct function in response to UV-irradiation.

  7. Von Hippel-Lindau tumor suppressor gene loss in renal cell carcinoma promotes oncogenic epidermal growth factor receptor signaling via Akt-1 and MEK-1.

    Science.gov (United States)

    Lee, S Justin; Lattouf, Jean-Baptiste; Xanthopoulos, Julie; Linehan, W Marston; Bottaro, Donald P; Vasselli, James R

    2008-10-01

    Clear-cell renal cell carcinoma (RCC) is the most prevalent form of kidney cancer and is frequently associated with loss of von Hippel-Lindau (VHL) gene function, resulting in the aberrant transcriptional activation of genes that contribute to tumor growth and metastasis, including transforming growth factor-alpha (TGF-alpha), a ligand of the epidermal growth factor receptor (EGFR) tyrosine kinase. To determine the functional impact of EGFR activation on RCC, we suppressed critical components of this pathway: EGFR, Akt-1, and MEK-1. Stable transfection of RCC cells with plasmids bearing shRNA directed against each of these genes was used to individually suppress their expression. Transfectants were characterized for growth and invasiveness in vitro and tumorigenesis in vivo. RCC cell transfectants displayed significantly reduced growth rate and matrix invasion in vitro and RCC tumor xenograft growth rate in vivo. Analysis of tumor cells that emerged after extended periods in each model showed that significant EGFR suppression was sustained, whereas Akt-1 and MEK-1 knock-down cells had escaped shRNA suppression. EGFR, Akt-1, and MEK-1 are individually critical for RCC cell invasiveness in vitro and tumorigenicity in vivo, and even partial suppression of each can have a significant impact on tumor progression. The emergence of transfectants that had escaped Akt-1 and MEK-1 suppression during tumorigenicity experiments suggests that these effectors may each be more critical than EGFR for RCC tumorigenesis, consistent with results from clinical trials of EGFR inhibitors for RCC, where durable clinical responses have not been seen.

  8. Von Hippel-Lindau Tumor Suppressor Gene Loss in Renal Cell Carcinoma Promotes Oncogenic Epidermal Growth Factor Receptor Signaling via Akt-1 and MEK1

    Science.gov (United States)

    Lee, S. Justin; Lattouf, Jean-Baptiste; Xanthopoulos, Julie; Linehan, W. Marston; Bottaro, Donald P.; Vasselli, James R.

    2008-01-01

    Objectives Clear-cell renal cell carcinoma (RCC) is the most prevalent form of kidney cancer and is frequently associated with loss of von Hippel-Lindau (VHL) gene function, resulting in the aberrant transcriptional activation of genes that contribute to tumor growth and metastasis, including transforming growth factor-α (TGF-α), a ligand of the epidermal growth factor receptor (EGFR) tyrosine kinase. To determine the functional impact of EGFR activation on RCC, we suppressed critical components of this pathway: EGFR, Akt-1, and MEK-1. Methods Stable transfection of RCC cells with plasmids bearing shRNA directed against each of these genes was used to individually suppress their expression. Transfectants were characterized for growth and invasiveness in vitro and tumorigenesis in vivo. Results RCC cell transfectants displayed significantly reduced growth rate and matrix invasion in vitro and RCC tumor xenograft growth rate in vivo. Analysis of tumor cells that emerged after extended periods in each model showed that significant EGFR suppression was sustained, whereas Akt-1 and MEK-1 knockdown cells had escaped shRNA suppression. Conclusions EGFR, Akt-1, and MEK-1 are individually critical for RCC cell invasiveness in vitro and tumorigenicity in vivo, and even partial suppression of each can have a significant impact on tumor progression. The emergence of transfectants that had escaped Akt-1 and MEK-1 suppression during tumorigenicity experiments suggests that these effectors may each be more critical than EGFR for RCC tumorigenesis, consistent with results from clinical trials of EGFR inhibitors for RCC, where durable clinical responses have not been seen. PMID:18243508

  9. Determining fissile content of nuclear fuel elements

    International Nuclear Information System (INIS)

    Arya, S.P.; Grossman, L.N.; Schoenig, F.C.

    1980-01-01

    This invention relates to the determination of the fissile fuel content of fuel for nuclear reactors. A nondestructive method is described for determining rapidly, accurately and simultaneously the fissile content, enrichment and location of fuel material which may also contain amounts of burnable poison, by detecting the γ-rays emitted from the fuel material due to natural radioactive decay. (U.K.)

  10. Ligand-based modeling of Akt3 lead to potent dual Akt1/Akt3 inhibitor.

    Science.gov (United States)

    Al-Sha'er, Mahmoud A; Taha, Mutasem O

    2018-02-13

    Akt1 and Akt3 are important serine/threonine-specific protein kinases involved in G2 phase required by cancer cells to maintain cell cycle and to prevent cell death. Accordingly, inhibitors of these kinases should have potent anti-cancer properties. This prompted us to use pharmacophore/QSAR modeling to identify optimal binding models and physicochemical descriptors that explain bioactivity variation within a set of 74 diverse Akt3 inhibitors. Two successful orthogonal pharmacophores were identified and further validated using receiver operating characteristic (ROC) curve analyses. The pharmacophoric models and associated QSAR equation were applied to screen the national cancer institute (NCI) list of compounds for new Akt3 inhibitors. Six hits showed significant experimental anti-Akt3 IC 50 values, out of which one compound exhibited dual low micromolar anti-Akt1 and anti-Akt3 inhibitory profiles. Copyright © 2018 Elsevier Inc. All rights reserved.

  11. Hepatic Proteomic Analysis Revealed Altered Metabolic Pathways in Insulin Resistant Akt1+/-/Akt2-/-Mice

    Science.gov (United States)

    Pedersen, Brian A; Wang, Weiwen; Taylor, Jared F; Khattab, Omar S; Chen, Yu-Han; Edwards, Robert A; Yazdi, Puya G; Wang, Ping H

    2015-01-01

    Objective The aim of this study was to identify liver proteome changes in a mouse model of severe insulin resistance and markedly decreased leptin levels. Methods Two-dimensional differential gel electrophoresis was utilized to identify liver proteome changes in AKT1+/-/AKT2-/- mice. Proteins with altered levels were identified with tandem mass spectrometry. Ingenuity Pathway analysis was performed for the interpretation of the biological significance of the observed proteomic changes. Results 11 proteins were identified from 2 biological replicates to be differentially expressed by a ratio of at least 1.3 between age-matched insulin resistant (Akt1+/-/Akt2-/-) and wild type mice. Albumin and mitochondrial ornithine aminotransferase were detected from multiple spots, which suggest post-translational modifications. Enzymes of the urea cycle were common members of top regulated pathways. Conclusion Our results help to unveil the regulation of the liver proteome underlying altered metabolism in an animal model of severe insulin resistance. PMID:26455965

  12. HAX-1 Protects Glioblastoma Cells from Apoptosis through the Akt1 Pathway

    Directory of Open Access Journals (Sweden)

    Xin Deng

    2017-12-01

    Full Text Available Glioblastoma is the most common malignant tumor in central nervous system (CNS, and it is still insurmountable and has a poor prognosis. The proliferation and survival mechanism of glioma cells needs to be explored further for the development of glioma treatment. Hematopoietic-substrate-1 associated protein X-1 (HAX-1 has been reported as an anti-apoptosis protein that plays an important role in several malignant tumors. However, the effect and mechanism of HAX-1 in glioblastomas remains unknown. This study aimed to investigate the effect of HAX-1 in glioblastoma cells and explore the mechanism. The results of clone formation and Edu proliferation assay showed slower multiplication in HAX-1 knock-out cells. Flow cytometry showed cell cycle arrest mainly in G0/G1 phase. Apoptosis due to oxidative stress was increased after HAX-1 was knocked out. Western-blot assay exhibited that the levels of p21, Bax, and p53 proteins were significantly raised, and that the activation of the caspase cascade was enhanced in the absence of HAX-1. The degradation rate and ubiquitination of p53 declined because of the decrease in phosphorylation of proteins MDM2 and Akt1. Co-immunoprecipitation (Co-IP and immunefluorescent co-localization assays were performed to test the influence of HAX-1 on the interaction between Akt1 and Hsp90, which is crucial for the activity of Akt1. In conclusion, this novel study suggested that HAX-1 could affect the Akt1 pathway through Hsp90. The knock-out of HAX-1 leads to the inactivity of the Ak1t/MDM2 axis, which leads to increased levels of p53, and finally generates cell cycle arrest and results in the apoptosis of glioblastoma cells.

  13. Determination of uranium traces in nuclear cans of nuclear reactors

    International Nuclear Information System (INIS)

    Acosta L, E.; Benavides M, A.M.; Sanchez P, L.

    1996-01-01

    To quantify the uranium content as impurity can be found in zirconium alloys and zircaloy, utilized to construct the sheaths containing fuels of the reactors of nuclear plants. The determination by fluorescence spectroscopy was employed as quality control measurement, at once the corrosion resistance, diminish with the increase of the uranium content in the alloys. (Author)

  14. miR-409-3p suppresses breast cancer cell growth and invasion by targeting Akt1

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Guoqiang [Department of Breast Surgery, Qilu Hospital, Shandong University, Jinan 250012 (China); Department of Thyroid and Breast Surgery, Hospital Affiliated to Binzhou Medical University, 661 Second Huanghe Street, Binzhou 256603 (China); Liu, Zengyan [Department of Hematology, Hospital Affiliated to Binzhou Medical University, 661 Second Huanghe Street, Binzhou 256603 (China); Xu, Hao [Department of General Surgery, The First Affiliated Hospital of Nanjing Medical University, Nanjing 210029 (China); Yang, Qifeng, E-mail: qifengy_sdu1@163.com [Department of Breast Surgery, Qilu Hospital, Shandong University, Jinan 250012 (China)

    2016-01-08

    Altered levels and functions of microRNAs (miRNAs) are correlated with carcinogenesis. While miR-409-3p has been shown to play important roles in several cancer types, its function in the context of breast cancer (BC) remains unknown. In this study, miR-409-3p was significantly downregulated in BC tissues and cell lines, compared with the corresponding control counterparts. Overexpression of miR-409-3p inhibited BC cell proliferation, migration and invasion in vitro and suppressed tumor growth in vivo. Notably, miR-409-3p induced downregulation of Akt1 protein through binding to its 3′ untranslated region (UTR). Conversely, restoring Akt1 expression rescued the suppressive effects of miR-409-3p. Our data collectively indicate that miR-409-3p functions as a tumor suppressor in BC through downregulating Akt1, supporting the targeting of the novel miR-409-3p/Akt1 axis as a potentially effective therapeutic approach for BC. - Highlights: • miR-409-3p inhibits proliferation, migration and invasion of BC cells. • miR-409-3p suppresses tumor growth in nude mice. • Akt1 is a direct downstream target of miR-409-3p. • Ectopic expression of Akt1 reverses the effects of miR-409-3p on cell proliferation, migration and invasion.

  15. Magnitude determination for large underground nuclear explosions

    Energy Technology Data Exchange (ETDEWEB)

    Porter, Lawrence D [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

    1970-05-15

    A method is presented for determining the local magnitudes for large underground nuclear explosions. The Gutenberg-Richter nomograph is applied to the peak amplitudes for 24 large underground nuclear explosions that took place in Nevada. The amplitudes were measured at 18 California Wood-Anderson stations located 150-810 km from the explosion epicenter. The variation of the individual station magnitudes and magnitude corrections and the variation of the average and rms error estimates in the magnitude determinations are examined with respect to distance, azimuth, and event location. The magnitude prediction capability of the Gutenberg-Richter nomograph is examined on the basis of these two criteria, and certain corrections are suggested. The azimuthal dependence of the individual station magnitudes is investigated, and corrections for the California stations are calculated. Statistical weighting schemes for two-component data are employed, and the assumptions and limitations in the use of peak amplitudes are discussed. (author)

  16. Activation of Akt1 accelerates carcinogen-induced tumorigenesis in mammary gland of virgin and post-lactating transgenic mice

    International Nuclear Information System (INIS)

    Wu, Yanyuan; Kim, Juri; Elshimali, Yayha; Sarkissyan, Marianna; Vadgama, Jaydutt V

    2014-01-01

    Data from in vivo and in vitro studies suggest that activation of Akt regulates cell survival signaling and plays a key role in tumorigenesis. Hence, transgenic mice were created to explore the oncogenic role of Akt1 in the development of mammary tumors. The transgenic mice were generated by expressing myristoylated-Akt1 (myr-Akt1) under the control of the MMTV-LTR promoter. The carcinogen 7, 12 dimethyl-1,2-benzanthracene (DMBA) was used to induce tumor formation. The MMTV driven myr-Akt1 transgene expression was detected primarily in the mammary glands, uterus, and ovaries. The expression level increased significantly in lactating mice, suggesting that the response was hormone dependent. The total Akt expression level in the mammary gland was also higher in the lactating mice. Interestingly, the expression of MMTVmyr-Akt1 in the ovaries of the transgenic mice caused significant increase in circulating estrogen levels, even at the post-lactation stage. Expression of myr-Akt1 in mammary glands alone did not increase the frequency of tumor formation. However, there was an increased susceptibility of forming mammary tumors induced by DMBA in the transgenic mice, especially in mice post-lactation. Within 34 weeks, DMBA induced mammary tumors in 42.9% of transgenic mice post-lactation, but not in wild-type mice post-lactation. The myr-Akt1 mammary tumors induced by DMBA had increased phosphorylated-Akt1 and showed strong expression of estrogen receptor (ERα) and epidermal growth factor receptor (EGFR). In addition, Cyclin D1 was more frequently up-regulated in mammary tumors from transgenic mice compared to tumors from wild-type mice. Overexpression of Cyclin D1, however, was not completely dependent on activated Akt1. Interestingly, mammary tumors that had metastasized to secondary sites had increased expression of Twist and Slug, but low expression of Cyclin D1. In summary, the MMTVmyr-Akt1 transgenic mouse model could be useful to study mechanisms of ER

  17. Determination of nuclear fuel burn-up

    International Nuclear Information System (INIS)

    Kristak, J.; Vobecky, M.

    1973-01-01

    Samples containing a known content of 235 U were irradiated with several different neutron doses and activities were determined of radionuclides including 125 Sb, 144 Ce, 134 Cs, 154 Eu, 103 Ru, 95 Zr. The values thus obtained were divided by the 137 Cs activity value. The resulting neutron dose-dependent value is plotted into a calibration graph. The degree of nuclear fuel burn-up is obtained from the graph using an experimentally determined ratio of the activities of the above radionuclides. (B.S.)

  18. Metabolic Transition of Milk Lactose Synthesis and Up-regulation by AKT1 in Sows from Late Pregnancy to Lactation.

    Science.gov (United States)

    Chen, Fang; Chen, Baoliang; Guan, Wutai; Chen, Jun; Lv, Yantao; Qiao, Hanzhen; Wang, Chaoxian; Zhang, Yinzhi

    2017-03-01

    Lactose plays a crucial role in controlling milk volume by inducing water toward into the mammary secretory vesicles from the mammary epithelial cell cytoplasm, thereby maintaining osmolality. In current study, we determined the expression of several lactose synthesis related genes, including glucose transporters (glucose transporter 1, glucose transporter 8, sodium-glucose cotransporter 1, sodium-glucose cotransporter 3, and sodium-glucose cotransporter 5), lactose synthases (α-lactalbumin and β1,4-galactosyltransferase), and hexokinases (hexokinase-1 and hexokinase-2) in sow mammary gland tissue at day 17 before delivery, on the 1st day of lactation and at peak lactation. The data showed that glucose transporter 1 was the dominant glucose transporter within sow mammary gland and that expression of each glucose transporter 1, sodium-glucose cotransporter 1, hexokinase-1, hexokinase-2, α-lactalbumin, and β1,4-galactosyltransferase were increased (p lactose synthesis was significantly elevated with the increase of milk production and AKT1 could positively regulate lactose synthesis.

  19. Spectroscopical determination of impurities in nuclear graphite

    International Nuclear Information System (INIS)

    Lordello, A.R.; Tognini, R.P.

    1975-01-01

    A spectrochemical method for the direct determination of B, Cd, Si, Hg, Fe, Mg, Mn, Cr, Ni, Al, Mo, Ti, Sr, Na, Zn, and As in nuclear grade graphite is described. A 9:1 ratio of graphite to copper difluoride is used in the preparation of samples and standards. The excitation is carried out in a d-c at 10 amperes. The copper fluoride used as spectrographic buffer serves to increase the volatilization rate of the impurities and to diminish the differences in the nature of the analytical and calibration samples. The relative standard deviations for the determination of the 16 trace elements, except Sr, Fe, Cd, Al and Si, are in the range of 8 - 20% in their appropriate calibration levels. For the latter five elements they are approximately 20-40%

  20. EGFR and AKT1 overexpression are mutually exclusive and associated with a poor survival in resected gastric adenocarcinomas.

    Science.gov (United States)

    Petrini, Iacopo; Lencioni, Monica; Vasile, Enrico; Fornaro, Lorenzo; Belluomini, Lorenzo; Pasquini, Giulia; Ginocchi, Laura; Caparello, Chiara; Musettini, Gianna; Vivaldi, Caterina; Caponi, Sara; Ricci, Sergio; Proietti, Agenese; Fontanini, Gabriella; Naccarato, Antonio Giuseppe; Nardini, Vincenzo; Santi, Stefano; Falcone, Alfredo

    2018-02-14

    The evaluation of molecular targets in gastric cancer has demonstrated the predictive role of HER2 amplification for trastuzumab treatment in metastatic gastric cancer. Besides HER2, other molecular targets are under evaluation in metastatic gastric tumors. However, very little is known about their role in resected tumors. We evaluated the expression of HER2, EGFR, MET, AKT1 and phospho-mTOR in resected stage II-III adenocarcinomas. Ninety-two patients with resected stomach (63%) or gastro-esophageal adenocarcinomas (27%) were evaluated. Antibodies anti-HER2, EGFR, MET, AKT1 and phospho-mTOR were used for immunostaining of formalin-fixed paraffin-embedded slides. Using FISH, HER2 amplification was evaluated in cases with an intermediate (+2) staining. EGFR overexpression (11%) was a poor prognostic factor for overall survival (3-year OS: 47% vs 77%; Log-Rank p= 0.033). MET overexpression (36%) was associated with a trend for a worse survival (3-year OS: 65% vs 77%; Log-Rank p= 0.084). HER2 amplification/overexpression and mTOR hyper-phosphorylation were observed in 13% and 48% of tumors, respectively. AKT1 overexpression (8%) was not a prognostic factor by itself (p= 0.234). AKT1 and EGFR overexpression was mutually exclusive and patients with EGFR or AKT1 overexpression experienced a poor prognosis (3-year OS: 52% vs. 79%, Log-Rank p= 0.005). EGFR is confirmed a poor prognostic factor in resected gastric cancers. We firstly describe a mutually exclusive overexpression of EGFR and AKT1 with potential prognostic implications, suggesting the relevance of this pathway for the growth of gastric cancers.

  1. PI3K/Akt1 signalling specifies foregut precursors by generating regionalized extra-cellular matrix

    DEFF Research Database (Denmark)

    Villegas, S Nahuel; Rothová, Michaela; Barrios-Llerena, Martin E

    2013-01-01

    -to-mesenchymal transition (EMT). Akt1 transduced this activity via modifications to the extracellular matrix (ECM) and appropriate ECM could itself induce anterior endodermal identity in the absence of PI3K signalling. PI3K/Akt1-modified ECM contained low levels of Fibronectin (Fn1) and we found that Fn1 dose was key...... to specifying anterior endodermal identity in vivo and in vitro. Thus, localized PI3K activity affects ECM composition and ECM in turn patterns the endoderm. DOI: http://dx.doi.org/10.7554/eLife.00806.001....

  2. Neuroprotective effect of nicorandil through inhibition of apoptosis by the PI3K/Akt1 pathway in a mouse model of deep hypothermic low flow.

    Science.gov (United States)

    Yu, Di; Fan, Changfeng; Zhang, Weiyan; Wen, Zhongyuan; Hu, Liang; Yang, Lei; Feng, Yu; Yin, Ke-Jie; Mo, Xuming

    2015-10-15

    Nicorandil exerts a protective effect on ischemia-reperfusion (I/R) injury in the brain and kidney through anti-apoptotic mechanisms. However, the mechanism by which nicorandil protects against I/R injury induced by deep hypothermic low flow (DHLF) remains unclear. We used a cerebral I/R model induced by DHLF to determine the neuroprotective effects and possible mechanisms of nicorandil. Hematoxylin-eosin (HE) staining and in situ terminal deoxynucleotidyl transferase UTP nick end labeling (TUNEL) assay were used to detect changes in cell morphology and the number of apoptotic cells in hippocampus, respectively. The apoptotic regulators including Bcl-2, Bax, Akt, and p-Akt (the active, phosphorylated form of Akt) were examined by Western blot (WB). Histopathological findings showed that nicorandil significantly alleviated morphological damage in hippocampal and reduced the number of TUNEL-positive nuclei induced by DHLF. Nicorandil also increased the expression of Bcl-2 and decreased the expression of Bax, while increasing p-Akt level. Consistent with these results, nicorandil-mediated neuroprotection was reduced in the Akt1+/- mutant mice and inhibited by LY294002, a PI3K inhibitor. These findings showed that nicorandil provides a neuroprotective role in DHLF-induced I/R injury by inhibiting apoptosis via activation of the PI3K/Akt1 signaling pathway. Copyright © 2015 Elsevier B.V. All rights reserved.

  3. Neurogenesis and Increase in Differentiated Neural Cell Survival via Phosphorylation of Akt1 after Fluoxetine Treatment of Stem Cells

    Directory of Open Access Journals (Sweden)

    Anahita Rahmani

    2013-01-01

    Full Text Available Fluoxetine (FLX is a selective serotonin reuptake inhibitor (SSRI. Its action is possibly through an increase in neural cell survival. The mechanism of improved survival rate of neurons by FLX may relate to the overexpression of some kinases such as Akt protein. Akt1 (a serine/threonine kinase plays a key role in the modulation of cell proliferation and survival. Our study evaluated the effects of FLX on mesenchymal stem cell (MSC fate and Akt1 phosphorylation levels in MSCs. Evaluation tests included reverse transcriptase polymerase chain reaction, western blot, and immunocytochemistry assays. Nestin, MAP-2, and β-tubulin were detected after neurogenesis as neural markers. Ten μM of FLX upregulated phosphorylation of Akt1 protein in induced hEnSC significantly. Also FLX did increase viability of these MSCs. Continuous FLX treatment after neurogenesis elevated the survival rate of differentiated neural cells probably by enhanced induction of Akt1 phosphorylation. This study addresses a novel role of FLX in neurogenesis and differentiated neural cell survival that may contribute to explaining the therapeutic action of fluoxetine in regenerative pharmacology.

  4. Determination of leakage areas in nuclear piping

    International Nuclear Information System (INIS)

    Keim, E.

    1997-01-01

    For the design and operation of nuclear power plants the Leak-Before-Break (LBB) behavior of a piping component has to be shown. This means that the length of a crack resulting in a leak is smaller than the critical crack length and that the leak is safely detectable by a suitable monitoring system. The LBB-concept of Siemens/KWU is based on computer codes for the evaluation of critical crack lengths, crack openings, leakage areas and leakage rates, developed by Siemens/KWU. In the experience with the leak rate program is described while this paper deals with the computation of crack openings and leakage areas of longitudinal and circumferential cracks by means of fracture mechanics. The leakage areas are determined by the integration of the crack openings along the crack front, considering plasticity and geometrical effects. They are evaluated with respect to minimum values for the design of leak detection systems, and maximum values for controlling jet and reaction forces. By means of fracture mechanics LBB for subcritical cracks has to be shown and the calculation of leakage areas is the basis for quantitatively determining the discharge rate of leaking subcritical through-wall cracks. The analytical approach and its validation will be presented for two examples of complex structures. The first one is a pipe branch containing a circumferential crack and the second one is a pipe bend with a longitudinal crack

  5. Determination of leakage areas in nuclear piping

    Energy Technology Data Exchange (ETDEWEB)

    Keim, E. [Siemens/KWU, Erlangen (Germany)

    1997-04-01

    For the design and operation of nuclear power plants the Leak-Before-Break (LBB) behavior of a piping component has to be shown. This means that the length of a crack resulting in a leak is smaller than the critical crack length and that the leak is safely detectable by a suitable monitoring system. The LBB-concept of Siemens/KWU is based on computer codes for the evaluation of critical crack lengths, crack openings, leakage areas and leakage rates, developed by Siemens/KWU. In the experience with the leak rate program is described while this paper deals with the computation of crack openings and leakage areas of longitudinal and circumferential cracks by means of fracture mechanics. The leakage areas are determined by the integration of the crack openings along the crack front, considering plasticity and geometrical effects. They are evaluated with respect to minimum values for the design of leak detection systems, and maximum values for controlling jet and reaction forces. By means of fracture mechanics LBB for subcritical cracks has to be shown and the calculation of leakage areas is the basis for quantitatively determining the discharge rate of leaking subcritical through-wall cracks. The analytical approach and its validation will be presented for two examples of complex structures. The first one is a pipe branch containing a circumferential crack and the second one is a pipe bend with a longitudinal crack.

  6. Determination of efficacy of nuclear medicine procedures

    International Nuclear Information System (INIS)

    Saenger, E.L.; Buncher, C.R.; Specker, B.; McDevitt, R.A.

    1984-01-01

    Nuclear medicine, a high technology field, is evaluated as to its usefulness. This paper describes the SNM study of 2023 patients comparing two methods evaluating efficacy for lung scanning (LS). Only the referring physicians determined the probabilities of the most important (MI) and most likely (ML) diagnoses and management before and after lung scanning. A logistic regression model was developed for probability of a signout diagnosis of PE. Equal patient groups tested the validity of the regression equations for the probability of PE as MI or ML. The models developed on Group I (G-I) and used on Group II (G-II) gave similar results. This shows that LS classifies PE and NOT PE categories where PE was considered both MI and ML. Entropy minimax pattern detection (EMPD) attempts prediction of signout diagnosis and management from prior patient attributes. In 2023 cases, attributes alone could not eliminate the use of LS for all patients. Comparing the two methods, the predictive values, sensitivity and specificity of each method are similar. EMPD predicts on a relatively small percent (40% before LS, 71% post LS) while the logistic equation predicts on 100% of the cases. An advantage of EMPD is that it does not require estimates of prior probability. However, LR, uses this estimate, thus incorporating intuitive knowledge not evaluated by EMPD. These methods are unique in showing that LS can direct the referring physician toward or away from anticoagulant therapy based on findings of the lung scan

  7. Constitutional determinants of nuclear power plant upgrading

    International Nuclear Information System (INIS)

    Mann, Thomas

    2013-01-01

    Around half a year ago the European stress test for nuclear power plants, a precautionary measure initiated by the European Council in March 2011 in response to the Fukushima disaster, revealed that while German nuclear power plants show a high degree of robustness compared with those in other European countries, they nevertheless required upgrading in one or the other respect (earthquake warning systems, protection against crashing civil passenger airplanes). The present article investigates whether this upgrading requirement can justify an injunction to carry out structural retrofitting measures or whether obligations to this end can be excluded on grounds of reasonability in view of the recent decision taken by the German parliament to phase out nuclear energy.

  8. Determination of action zone in the nuclear / radiology handling process

    International Nuclear Information System (INIS)

    Ade Awalludin

    2013-01-01

    Assessment has been conducted on determination of action zone in nuclear or radiological emergency. The assessment is taken into account radiological risk level in nuclear or radiological emergency management process outside nuclear installation. Managing of nuclear emergency is same as that one of other emergency by adding the principles of radiation protection. This study aims to provide guidance in making of safety and security perimeter outside the nuclear installation for first responders during nuclear/radiological emergency based on dose rate, contamination level or distance from the scene. Separation of working zone is important for first responder safety that works in radiological environment in the event of nuclear or radiation emergency without violating their standard operating procedure. Value limit of safety and security perimeter has been made according to the conditions in Indonesia and considering the applicability in practical. (author)

  9. Nuclear forensics and nuclear analytical chemistry - iridium determination in a referred forensic sample

    International Nuclear Information System (INIS)

    Basu, A.K.; Bhadkambekar, C.A.; Tripathi, A.B.R.; Chattopadhyay, N.; Ghosh, P.

    2010-01-01

    Nuclear approaches for compositional characterization has bright application prospect in forensic perspective towards assessment of nature and origin of seized material. The macro and micro physical properties of nuclear materials can be specifically associated with a process or type of nuclear activity. Under the jurisdiction of nuclear analytical chemistry as well as nuclear forensics, thrust areas of scientific endeavor like determination of radioisotopes, isotopic and mass ratios, analysis for impurity contents, arriving at chemical forms/species and physical parameters play supporting evidence in forensic investigations. The analytical methods developed for this purposes can be used in international safeguards as well for nuclear forensics. Nuclear material seized in nuclear trafficking can be identified and a profile of the nuclear material can be created

  10. Determination of the origin of unknown irradiated nuclear fuel.

    Science.gov (United States)

    Nicolaou, G

    2006-01-01

    An isotopic fingerprinting method is presented to determine the origin of unknown nuclear material with forensic importance. Spent nuclear fuel of known origin has been considered as the 'unknown' nuclear material in order to demonstrate the method and verify its prediction capabilities. The method compares, using factor analysis, the measured U, Pu isotopic compositions of the 'unknown' material with U, Pu isotopic compositions simulating well known spent fuels from a range of commercial nuclear power stations. Then, the 'unknown' fuel has the same origin as the commercial fuel with which it exhibits the highest similarity in U, Pu compositions.

  11. Determination of the origin of unknown irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Nicolaou, G.

    2006-01-01

    An isotopic fingerprinting method is presented to determine the origin of unknown nuclear material with forensic importance. Spent nuclear fuel of known origin has been considered as the 'unknown' nuclear material in order to demonstrate the method and verify its prediction capabilities. The method compares, using factor analysis, the measured U, Pu isotopic compositions of the 'unknown' material with U, Pu isotopic compositions simulating well known spent fuels from a range of commercial nuclear power stations. Then, the 'unknown' fuel has the same origin as the commercial fuel with which it exhibits the highest similarity in U, Pu compositions

  12. Kaempferol Suppresses Transforming Growth Factor-β1-Induced Epithelial-to-Mesenchymal Transition and Migration of A549 Lung Cancer Cells by Inhibiting Akt1-Mediated Phosphorylation of Smad3 at Threonine-179.

    Science.gov (United States)

    Jo, Eunji; Park, Seong Ji; Choi, Yu Sun; Jeon, Woo-Kwang; Kim, Byung-Chul

    2015-07-01

    Kaempferol, a natural dietary flavonoid, is well known to possess chemopreventive and therapeutic anticancer efficacy; however, its antimetastatic effects have not been mechanistically studied so far in any cancer model. This study was aimed to investigate the inhibitory effect and accompanying mechanisms of kaempferol on epithelial-to-mesenchymal transition (EMT) and cell migration induced by transforming growth factor-β1 (TGF-β1). In human A549 non-small lung cancer cells, kaempferol strongly blocked the enhancement of cell migration by TGF-β1-induced EMT through recovering the loss of E-cadherin and suppressing the induction of mesenchymal markers as well as the upregulation of TGF-β1-mediated matrix metalloproteinase-2 activity. Interestingly, kaempferol reversed TGF-β1-mediated Snail induction and E-cadherin repression by weakening Smad3 binding to the Snail promoter without affecting its C-terminus phosphorylation, complex formation with Smad4, and nuclear translocation under TGF-β1 stimulation. Mechanism study revealed that the phosphorylation of Smad3 linker region induced by TGF-β1 was required for the induction of EMT and cell migration, and selective downregulation of the phosphorylation of Smad3 at Thr179 residue (not Ser204, Ser208, and Ser213) in the linker region was responsible for the inhibition by kaempferol of TGF-β1-induced EMT and cell migration. Furthermore, Akt1 was required for TGF-β1-mediated induction of EMT and cell migration and directly phosphorylated Smad3 at Thr179, and kaempferol completely abolished TGF-β1-induced Akt1 phosphorylation. In summary, kaempferol blocks TGF-β1-induced EMT and migration of lung cancer cells by inhibiting Akt1-mediated phosphorylation of Smad3 at Thr179 residue, providing the first evidence of a molecular mechanism for the anticancer effect of kaempferol. Copyright © 2015 The Authors. Published by Elsevier Inc. All rights reserved.

  13. Kaempferol Suppresses Transforming Growth Factor-β1–Induced Epithelial-to-Mesenchymal Transition and Migration of A549 Lung Cancer Cells by Inhibiting Akt1-Mediated Phosphorylation of Smad3 at Threonine-1791

    Science.gov (United States)

    Jo, Eunji; Park, Seong Ji; Choi, Yu Sun; Jeon, Woo-Kwang; Kim, Byung-Chul

    2015-01-01

    Kaempferol, a natural dietary flavonoid, is well known to possess chemopreventive and therapeutic anticancer efficacy; however, its antimetastatic effects have not been mechanistically studied so far in any cancer model. This study was aimed to investigate the inhibitory effect and accompanying mechanisms of kaempferol on epithelial-to-mesenchymal transition (EMT) and cell migration induced by transforming growth factor-β1 (TGF-β1). In human A549 non–small lung cancer cells, kaempferol strongly blocked the enhancement of cell migration by TGF-β1–induced EMT through recovering the loss of E-cadherin and suppressing the induction of mesenchymal markers as well as the upregulation of TGF-β1–mediated matrix metalloproteinase-2 activity. Interestingly, kaempferol reversed TGF-β1–mediated Snail induction and E-cadherin repression by weakening Smad3 binding to the Snail promoter without affecting its C-terminus phosphorylation, complex formation with Smad4, and nuclear translocation under TGF-β1 stimulation. Mechanism study revealed that the phosphorylation of Smad3 linker region induced by TGF-β1 was required for the induction of EMT and cell migration, and selective downregulation of the phosphorylation of Smad3 at Thr179 residue (not Ser204, Ser208, and Ser213) in the linker region was responsible for the inhibition by kaempferol of TGF-β1–induced EMT and cell migration. Furthermore, Akt1 was required for TGF-β1–mediated induction of EMT and cell migration and directly phosphorylated Smad3 at Thr179, and kaempferol completely abolished TGF-β1–induced Akt1 phosphorylation. In summary, kaempferol blocks TGF-β1–induced EMT and migration of lung cancer cells by inhibiting Akt1-mediated phosphorylation of Smad3 at Thr179 residue, providing the first evidence of a molecular mechanism for the anticancer effect of kaempferol. PMID:26297431

  14. The determination of nuclear matter temperature and density

    International Nuclear Information System (INIS)

    Wolf, K.L.

    1981-01-01

    The purpose of this paper is to review some of the things we have learned about nuclear matter under extreme conditions during the past few years in relativistic heavy ion studies. High energy heavy-ion collisions provide a unique mechanism for exploring the dependence of the nuclear potential energy epsilon(rho,T) on the degree of compression and excitation, and may even show the existence of new phases of matter. Thus the determination of the nuclear equation of state remains the ultimate goal of many researchers in this field. (orig.)

  15. Nuclear yield determinations using isotope-separator-on-line arrangements

    International Nuclear Information System (INIS)

    Rudstam, G.

    1975-01-01

    The delay between the formation of a nuclear reaction product and its collection in front of measuring equipment in ISOL arrangements using integrated target-ion source systems has been analyzed. It is shown that a typical delay function takes the form const x (1-esup(-γt))esup(-μt) with γ >> μ. The results can be used for decay corrections in nuclear yield determinations. (Auth.)

  16. Reactive Oxygen Species-Mediated Loss of Synaptic Akt1 Signaling Leads to Deficient Activity-Dependent Protein Translation Early in Alzheimer's Disease.

    Science.gov (United States)

    Ahmad, Faraz; Singh, Kunal; Das, Debajyoti; Gowaikar, Ruturaj; Shaw, Eisha; Ramachandran, Arathy; Rupanagudi, Khader Valli; Kommaddi, Reddy Peera; Bennett, David A; Ravindranath, Vijayalakshmi

    2017-12-01

    Synaptic deficits are known to underlie the cognitive dysfunction seen in Alzheimer's disease (AD). Generation of reactive oxygen species (ROS) by β-amyloid has also been implicated in AD pathogenesis. However, it is unclear whether ROS contributes to synaptic dysfunction seen in AD pathogenesis and, therefore, we examined whether altered redox signaling could contribute to synaptic deficits in AD. Activity dependent but not basal translation was impaired in synaptoneurosomes from 1-month old presymptomatic APP Swe /PS1ΔE9 (APP/PS1) mice, and this deficit was sustained till middle age (MA, 9-10 months). ROS generation leads to oxidative modification of Akt1 in the synapse and consequent reduction in Akt1-mechanistic target of rapamycin (mTOR) signaling, leading to deficiency in activity-dependent protein translation. Moreover, we found a similar loss of activity-dependent protein translation in synaptoneurosomes from postmortem AD brains. Loss of activity-dependent protein translation occurs presymptomatically early in the pathogenesis of AD. This is caused by ROS-mediated loss of pAkt1, leading to reduced synaptic Akt1-mTOR signaling and is rescued by overexpression of Akt1. ROS-mediated damage is restricted to the synaptosomes, indicating selectivity. We demonstrate that ROS-mediated oxidative modification of Akt1 contributes to synaptic dysfunction in AD, seen as loss of activity-dependent protein translation that is essential for synaptic plasticity and maintenance. Therapeutic strategies promoting Akt1-mTOR signaling at synapses may provide novel target(s) for disease-modifying therapy in AD. Antioxid. Redox Signal. 27, 1269-1280.

  17. Burnup determination of mass spectrometry for nuclear fuels

    International Nuclear Information System (INIS)

    Zhang Chunhua.

    1987-01-01

    The various methods currently being used in burnup determination of nuclear fuels are studied and reviewed. The mass spectrometry method of destructive testing is discussed emphatically. The burnup determination of mass spectrometry includes heavy isotopic abundance ratio method and isotope dilution mass spectrometry used as burnup indicator for the fission products. The former is applied to high burnup level, but the later to various burnup level. According to experiences, some problems which should be noticed in burnup determination of mass spectrometry are presented

  18. An approach for determining the acceptable levels of nuclear risk

    International Nuclear Information System (INIS)

    1978-03-01

    The objective of this study was to develop a methodology for determining the acceptable levels of risk with respect to nuclear energy. It was concluded that the Atomic Energy Control Board should identify the interest groups that affect its choice of an acceptable level of risk, determine their expectations, and balance the expectations of the various groups such that the resulting acceptable level of risk is still acceptable to the Board. This would be done by interviewing experts on the subject of nuclear safety, developing and pretesting a public questionnaire, and surveying the public on acceptable cost-risk combinations

  19. Using nuclear methods for analyzing materials and determining concentration gradients

    International Nuclear Information System (INIS)

    Darras, R.

    After reviewing the various type of nuclear chemical analysis methods, the possibilities of analysis by activation and direct observation of nuclear reactions are specifically described. These methods make it possible to effect analyses of trace-elements or impurities, even as traces, in materials, with selectivity, accuracy and great sensitivity. This latter property makes them advantageous too for determining major elements in small quantities of available matter. Furthermore, they lend themselves to carrying out superficial analyses and the determination of concentration gradients, given the careful choice of the nature and energy of the incident particles. The paper is illustrated with typical examples of analyses on steels, pure iron, refractory metals, etc [fr

  20. nuclear and atomic methods applied in the determination of some

    African Journals Online (AJOL)

    NAA is a quantitative and qualitative method for the precise determination of a number of major, minor and trace elements in different types of geological, environmental and biological samples. It is based on nuclear reaction between neutron and target nuclei of a sample material. It is a useful method for the simultaneous.

  1. Determination of 93Zr in nuclear power plant wastes

    DEFF Research Database (Denmark)

    Osváth, Szabolcs; Vajda, Nora; Molnar, Zsuzsa

    2017-01-01

    A radioanalytical method (based on separation using UTEVA columns and ICP-MS measurement) has been used for determination of 93Zr in 37 nuclear power plant samples. As 93Nb might affect the detection of 93Zr, Monte Carlo activation model was used to calculate the expected 93Zr/natZr mass ratio...

  2. Regulation of mTORC1 Signaling by Src Kinase Activity Is Akt1-Independent in RSV-Transformed Cells

    Directory of Open Access Journals (Sweden)

    Martina Vojtěchová

    2008-02-01

    Full Text Available Increased activity of the Src tyrosine protein kinase that has been observed in a large number of human malignancies appears to be a promising target for drug therapy. In the present study, a critical role of the Src activity in the deregulation of mTOR signaling pathway in Rous sarcoma virus (RSV-transformed hamster fibroblasts, H19 cells, was shown using these cells treated with the Src-specific inhibitor, SU6656, and clones of fibroblasts expressing either the active Src or the dominant-negative Src kinase-dead mutant. Disruption of the Src kinase activity results in substantial reduction of the phosphorylation and activity of the Akt/protein kinase B (PKB, phosphorylation of tuberin (TSC2, mammalian target of rapamycin (mTOR, S6K1, ribosomal protein S6, and eukaryotic initiation factor 4E-binding protein 4E-BP1. The ectopic, active Akt1 that was expressed in Src-deficient cells significantly enhanced phosphorylation of TSC2 in these cells, but it failed to activate the inhibited components of the mTOR pathway that are downstream of TSC2. The data indicate that the Src kinase activity is essential for the activity of mTOR-dependent signaling pathway and suggest that mTOR targets may be controlled by Src independently of Akt1/TSC2 cascade in cells expressing hyperactive Src protein. These observations might have an implication in drug resistance to mTOR inhibitor-based cancer therapy in certain cell types.

  3. DRD2/AKT1 interaction on D2 c-AMP independent signaling, attentional processing, and response to olanzapine treatment in schizophrenia.

    Science.gov (United States)

    Blasi, Giuseppe; Napolitano, Francesco; Ursini, Gianluca; Taurisano, Paolo; Romano, Raffaella; Caforio, Grazia; Fazio, Leonardo; Gelao, Barbara; Di Giorgio, Annabella; Iacovelli, Luisa; Sinibaldi, Lorenzo; Popolizio, Teresa; Usiello, Alessandro; Bertolino, Alessandro

    2011-01-18

    The D2/AKT1/GSK-3β signaling pathway has been involved in the downstream intracellular effects of dopamine, in the pathophysiology of cognitive deficits and related brain activity in schizophrenia, as well as in response to treatment with antipsychotics. Polymorphisms in the D2 (DRD2 rs1076560) and AKT1 (AKT1 rs1130233) genes have been associated with their respective protein expression and with higher-order cognition and brain function, including attention. Given the strong potential for their relationship, we investigated the interaction of these polymorphisms on multiple molecular and in vivo phenotypes associated with this signaling pathway. We measured AKT1 and GSK-3β proteins and phosphorylation in human peripheral blood mononuclear cells, functional MRI cingulate response during attentional control, behavioral accuracy during sustained attention, and response to 8 wk of treatment with olanzapine in a total of 190 healthy subjects and 66 patients with schizophrenia. In healthy subjects, we found that the interaction between the T allele of DRD2 rs1076560 and the A allele of AKT1 rs1130233 was associated with reduced AKT1 protein levels and reduced phosphorylation of GSK-3β, as well as with altered cingulate response and reduced behavioral accuracy during attentional processing. On the other hand, interaction of these two alleles was associated with greater improvement of Positive and Negative Syndrome Scale scores in patients with schizophrenia after treatment with olanzapine. The present results indicate that these functional polymorphisms are epistatically associated with multiple phenotypes of relevance to schizophrenia. Our results also lend support to further investigation of this downstream molecular pathway in the etiology and treatment of this disorder.

  4. The future of nuclear power determines tasks of Ukraines nuclear fuel cycle

    International Nuclear Information System (INIS)

    Paton, B.Ye.; Neklyudov, I.M.; Krasnorutskij, V.S.

    2013-01-01

    This study provides a brief analysis on the status and development of nuclear power in the world. The present results of physical and engineering development demonstrate that in the longer term, nuclear energy as a key macro energy source is able to secure the existence and development of mankind. Based on the demand for sustainable socioeconomic existence of Ukraine as a state, there have been determined major tasks for the development of nuclear fuel cycle of Ukraine that have to be implemented at present and in the medium term

  5. Self-consistent determination of quasiparticle properties in nuclear matter

    International Nuclear Information System (INIS)

    Oset, E.; Palanques-Mestre, A.

    1981-01-01

    The self-energy of nuclear matter is calculated by directing the attention to the energy and momentum dependent pieces which determine the quasiparticle properties. A microscopic approach is followed which starts from the boson exchange picture for the NN interaction, then the π-and p-mesons are shown to play a major role in the nucleon renormalization. The calculation is done self-consistently and the effective mass and pole strength determined as a function of the nuclear density and momentum. Particular emphasis is put on the non-static character of the interaction and its consequences. Finally a comparison is made with other calculations and with experimental results. The consequences of the nucleon renormalization in pion condensation are also examined with the result that the critical density is pushed up appreciably. (orig.)

  6. Determination of chlorine in nuclear-grade uranium compounds

    International Nuclear Information System (INIS)

    Yang Chunqing; Liu Fuyun; Huang Dianfan

    1988-01-01

    The determination of chlorine in nuclear-grade uranium compounds is discribed. Chlorine is separated from uranium oxide pyrohydrolytically with stream of wet oxygen in a furnace at 800 ∼ 900 deg C. Chlorine is volatilized as hydrochloric acid, absorbed in a dilute alkaline solution and measured with chlorine-selective electrode. This method covers the concentration range of 10 ∼ 500 pm chlorine in uranium oxide. Precision of at least ± 10% and recovery of 85 ∼ 108% have been reported

  7. The Masticatory Contractile Load Induced Expression and Activation of Akt1/PKBα in Muscle Fibers at the Myotendinous Junction within Muscle-Tendon-Bone Unit

    Directory of Open Access Journals (Sweden)

    Yüksel Korkmaz

    2010-01-01

    Full Text Available The cell specific detection of enzyme activation in response to the physiological contractile load within muscle-tendon-bone unit is essential for understanding of the mechanical forces transmission from muscle cells via tendon to the bone. The hypothesis that the physiological mechanical loading regulates activation of Akt1/PKBα at Thr308 and at Ser473 in muscle fibers within muscle-tendon-bone unit was tested using quantitative immunohistochemistry, confocal double fluorescence analysis, and immunoblot analysis. In comparison to the staining intensities in peripheral regions of the muscle fibers, Akt1/PKBα was detected with a higher staining intensity in muscle fibers at the myotendinous junction (MTJ areas. In muscle fibers at the MTJ areas, Akt1/PKBα is dually phosphorylated at Thr308 and Ser473. The immunohistochemical results were confirmed by immunoblot analysis. We conclude that contractile load generated by masticatory muscles induces local domain-dependent expression of Akt1/PKBα as well as activation by dually phosphorylation at Thr308 and Ser473 in muscle fibers at the MTJ areas within muscle-tendon-bone unit.

  8. Nuclear fuel technology - Determination of uranium in uranyl nitrate solutions of nuclear grade quality - Gravimetric method

    International Nuclear Information System (INIS)

    2003-01-01

    This International Standard specifies a precise and accurate gravimetric method for determining the mass fraction of uranium in uranyl nitrate solutions of nuclear grade quality containing more than 100 g/kg of uranium. Non-volatile impurities influence the accuracy of the method

  9. US Nuclear Non-Proliferation Policy: impact on exports and nuclear industry could not be determined

    International Nuclear Information System (INIS)

    Staats, E.B.

    1980-01-01

    The Nuclear Non-Proliferation Act of 1978 established new measures to prevent the diversion to weapons use of peaceful nuclear exports. It also created a policy to confirm US reliability as a nuclear supplier. GAO did not identify any export sales lost as a result of the Act, but did find indications that nonprofileration policies can influence export sales. Based on avavailable data, GAO could not determine the impact of the Act on the competitiveness of US nuclear exports. However, US companies are at some disadvantage because importers perceive that implementation of the Act may result in delayed export licenses. The United States dominated the nuclear export market through the early 1970s. However, foreign competitors, some aided by US technology transfers, emerged to monopolize home markets and complete for third-country business. Further, the market has been depressed since 1974 and prospects for US nuclear power plant exports have dimmed greatly. However, US companies continue to view exports as important to sustain production capacity

  10. Model for the determination of the nuclear fuel

    International Nuclear Information System (INIS)

    Azevedo, J.B.L. de.

    1979-09-01

    The Nuclear Fuel Cost Determination Model, MDCN, is a computer program written in FORTRAN IV, meant to calculate the nuclear fuel cost employed in nuclear power plants for heat or electrical energy generation. The economic principles employed are: capital recovery proportional to the energy generation, present worth method for the equivalence of costs and levelized fuel cost calculation. This model presents some inovations in comparasion with other models already in use, since it takes into account refueling and maintenance outages and it does not fix the fuel cycle steps (industrial processes and services). The first inovation leads to a more realistic cost determination and permits the model to be employed together with hydrothermal power system simulators; the second permits a more flexible use of the model, like economical comparison of fuel cycles. Complementing the main body of the work, where the theoretical fundamentals and methodology necessary to the calculation developments are discussed, annexes are included treating in greater detail some specific itens; the more important ones refer to the FORTRAN program, input data preparation and example. (Author) [pt

  11. A knowledge based method for nuclear plant loading pattern determination

    International Nuclear Information System (INIS)

    Dauboin, P.

    1990-01-01

    This paper deals with the design of a knowledge based system for solving an industrial problem which occurs in nuclear fuel management. The problem lies in determining satisfactory loading patterns for nuclear plants. Its primary feature consists in the huge search space involved. Conventional resolution processes are formally defined and analyzed: there is no general algorithm which guarantees to always provide a reasonable solution in each situation. We propose a new approach to solve this constrained search problem using domain-specific knowledge and general constraint-based heuristics. During a preprocessing step, a problem dependent search algorithm is designed. This procedure is then automatically implemented in FORTRAN. The generated routines have proved to be very efficient finding solutions which could not have been provided using logic programming. A prototype expert system has already been applied to actual reload pattern searches. While combining efficiency and flexibility, this knowledge based system enables human experts to rapidly match new constraints and requirements

  12. chemical determination of burnup ratio in nuclear fuels

    International Nuclear Information System (INIS)

    Guereli, L.

    1997-01-01

    Measurements of the extent of fission are important to determine the irradiation performance of a nuclear fuel. The energy released per unit mass of uranium (burnup) can be determined from measurement of the percent of heavy atoms that have fissioned during irradiation.The preferred method for this determination is choosing a suitable fission monitor (usually ''1''4''8Nd) and its determination after separation from the fuel matrix. In thermal reactor fuels where the only heavy element in the starting material is uranium, uranium depletion can be used for burnup determination. ''2''3''5U depletion method requires measurement of uranium isotopic ratios of both irradiated and unirradiated fuel. Isotopic ratios can be determined by thermal ionization mass spectrometer following separation of uranium from the fuel matrix. Separation procedures include solvent extraction, ion exchange and anion exchange chromatography. Another fission monitor used is ''1''3''9La determination by HPLC. Because La is monoisotopic (''1''3''9La) in the fuel, it can be determined by chemical analysis techniques

  13. Determination of 36Cl in nuclear waste from reactor decommissioning

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Frøsig, Lars; Nielsen, Sven Poul

    2007-01-01

    An analytical method for the determination of Cl-36 in nuclear waste such as graphite, heavy concrete, steel, aluminum, and lead was developed. Several methods were investigated for decomposing the samples. AgCl precipitation was used to separate Cl-36 from the matrix elements, followed by ion......-exchange chromatography to remove interfering radionuclides. The purified Cl-36 was then measured by liquid scintillation counting. The chemical yield of chlorine, as measured by ICPMS, is above 70% and the decontamination factors for all interfering radionuclides are greater than 10(6). The detection limit...

  14. Determination of palladium in biological samples applying nuclear analytical techniques

    International Nuclear Information System (INIS)

    Cavalcante, Cassio Q.; Sato, Ivone M.; Salvador, Vera L. R.; Saiki, Mitiko

    2008-01-01

    This study presents Pd determinations in bovine tissue samples containing palladium prepared in the laboratory, and CCQM-P63 automotive catalyst materials of the Proficiency Test, using instrumental thermal and epithermal neutron activation analysis and energy dispersive X-ray fluorescence techniques. Solvent extraction and solid phase extraction procedures were also applied to separate Pd from interfering elements before the irradiation in the nuclear reactor. The results obtained by different techniques were compared against each other to examine sensitivity, precision and accuracy. (author)

  15. Determination of air pollutants by nuclear chemical analysis

    International Nuclear Information System (INIS)

    Lesny, J.; Toelgyessy, J.

    1975-01-01

    Nuclear analytical methods are discussed with a view to their applicability in the determination of air pollutants. It is shown that some methods (use of radioactive kryptonates in automatic analyzers, application of activation analysis, X-ray fluorescence methods) are developed in theory and proven in practice in such an extent to be widely used in the near future in the control of the environment. Many other methods are becoming increasingly important for the solution of specific problems of environmental protection (such as the control of sudden environmental contamination in the proximity of chemical plants and industrial centers). (author)

  16. Determination of acceptable risk criteria for nuclear waste management

    International Nuclear Information System (INIS)

    Cohen, J.J.

    1977-01-01

    The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey

  17. Determination of plutonium 241 in solutions of nuclear wastes

    International Nuclear Information System (INIS)

    Raymond, A.; Bilcot, J.B.; Poletiko, C.

    1990-09-01

    Determination of plutonium 241 in nuclear wastes is important because of long period and high energy of some daughter products. In this report are presented two quantitative analysis methods using both scintillation techniques: A complete method, in any case, by selective extraction of plutonium on an anionic resin allowing simultaneous determination of Pu 241 and the sum of other plutonium isotopes; a simplified method when alpha activity is higher than beta/gamma activity by liquid extraction with TTA. These methods are applied for analysis of 4 waste types: cement encapsulated wastes, bitumen encapsulated wastes, incineration ashes, leaching of encapsulated incineration ashes. In these 4 examples, Pu 241 activity is equal or higher than the sum of alpha plutonium isotope activity. Separation efficiency, measured from Pu 239 or with Pu 236 as tracer, is between 90 and 99% [fr

  18. Determination of acceptable risk criteria for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, J.J.

    1977-10-21

    The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey.

  19. Determination of soluble carbon in nuclear grade boron carbide

    International Nuclear Information System (INIS)

    Vega Bustillos, J.O.; Gomes, R.; Camaro, J.; Zorzetto, F.; Domingues, P.; Riella, H.

    1990-05-01

    The present work describes two different techniques (manometric and wet chemical) for the soluble carbon determination in nuclear grade boron carbide. The techniques are based on the reaction of the boron carbide with a sulfocromic mixture, generating CO 2 . The techniques differ on the mode they do the measurement of CO 2 produced. By wet chemical technique the CO 2 is absorved in a barium hydroxide solution and is determinated by titration. In the manometric technique the CO 2 gas is measured using a McLeod gauge. The gas produced by the latter technique is analysed by mass spectrometry. The details of the analytical technique and the data obtained are discussed. (author) [pt

  20. Subcriticality determination of nuclear fuel assembly by Mihalczo method

    International Nuclear Information System (INIS)

    Yamane, Yoshihiro; Watanabe, Shoji; Nishina, Kojiro; Miyoshi, Yoshinori; Suzaki, Takenori; Kobayashi, Iwao.

    1986-01-01

    To establish a technique of on-site subcriticality determination suitable for the criticality safety management of nuclear fuel assembly, the applicability of the method proposed by Mihalczo was examined with the Tank-type Critical Assembly (TCA) of the Japan Atomic Energy Research Institute. In the Mihalczo method, cross power spectral densities and auto power spectral densities are evaluated from the output currents of an ionization chamber containing 252 Cf neutron source and two neutron detectors. The principle of this method is that the spectral ratio formed by the power spectral densities mentioned can be related to the subcriticality by the help of a stochastic theory. Throughout our data processing, an improved formula taking account of the neutron extinction at a detection process was used. Up to the subcriticality of 15 dollars, the Mihalczo method agreed with the water-level worth method, which has been a standard method of reactivity determination at the TCA facility. The systems treated in the present report hold symmetry concerning the nuclear fuel configuration and the 252 Cf chamber position. It was clarified that, contrary to Mihalczo's assertion, the factor converting the spectral ratio to a subcriticality depends on subcriticality itself. (author)

  1. India and Iran's nuclear issue: the three policy determinants

    International Nuclear Information System (INIS)

    Rajiv, S. Samuel C.

    2011-01-01

    Three broad policy determinants can be discerned in Indian reactions to the Iranian nuclear issue. These include: 'strategic autonomy' as it relates to Indian foreign policy decision making; concerns regarding 'regional strategic stability' as it relates to events in its 'proximate neighbourhood'; and 'national security' implications on account of operative clandestine proliferation networks. Issues relating to the role of the US in influencing Indian policy positions at international forums and vis-a-vis domestic policy were prominent as regards the first determinant. Threats and 'advice' by American policy makers and law makers on specific issues like the Indo-US nuclear deal and the Iran-Pakistan-India gas pipeline gave further grist to critics. However, an analysis of India's concerns regarding the other two policy considerations, i.e., strategic stability and national security were 'real and present' and also dominated public discourse as well. With India having become a non-permanent member of the UN Security Council from January 2011, it should be the task of Indian diplomacy, at the UNSC as well as at other bilateral and multilateral settings, to help expand the space for the application of 'satisfactory strategies' and reduce the range of 'unsatisfactory strategies'. (author)

  2. Separation and determination of strontium-90 in burnout nuclear fuel

    International Nuclear Information System (INIS)

    Khermann, A.; Katsvinkel', I.

    1975-01-01

    Developed was a simple and selective chromatographic method of the separation of strontium-90, by the content of which it is possible to judge about the degree of nuclear fuel burnup. Among the studied ion exchangers for strontium separation the best results are exhibited by strongly acidic organic cationite, i.e. vofatite (on the base of styrene, 8%-divinylbenzene) in the H + form. Elution was performed by hydrochloric or oxalic acids. The method allows to achieve a high degree of Sr-90 purification from other fission products. Using the method the Sr-90 content was determined in burnup fuel of the fuel elements of EK-10 type. At the fuel storage period less than 2 years it becomes necessary to determine both Sr-90 and Sr-89. Determination of Sr-90 in the presence of Sr-89 was made by daughter product of Sr-90 - Y-90, which is separated in ion-exchange coloumn. Some other methods of Sr-90 determination in the presence of Sr-89 are noted

  3. AS1411-Induced Growth Inhibition of Glioma Cells by Up-Regulation of p53 and Down-Regulation of Bcl-2 and Akt1 via Nucleolin.

    Directory of Open Access Journals (Sweden)

    Ye Cheng

    Full Text Available AS1411 binds nucleolin (NCL and is the first oligodeoxynucleotide aptamer to reach phase I and II clinical trials for the treatment of several cancers. However, the mechanisms by which AS1411 targets and kills glioma cells and tissues remain unclear. Here we report that AS1411 induces cell apoptosis and cycle arrest, and inhibits cell viability by up-regulation of p53 and down-regulation of Bcl-2 and Akt1 in human glioma cells. NCL was overexpressed in both nucleus and cytoplasm in human glioma U87, U251 and SHG44 cells compared to normal human astrocytes (NHA. AS1411 bound NCL and inhibited the proliferation of glioma cells but not NHA, which was accompanied with up-regulation of p53 and down-regulation of Bcl-2 and Akt1. Moreover, AS1411 treatment resulted in the G2/M cell cycle arrest in glioma cells, which was however abolished by overexpression of NCL. Further, AS1411 induced cell apoptosis, which was prevented by silencing of p53 and overexpression of Bcl-2. In addition, AS1411 inhibited the migration and invasion of glioma cells in an Akt1-dependent manner. Importantly, AS1411 inhibited the growth of glioma xenograft and prolonged the survival time of glioma tumor-bearing mice. These results revealed a promising treatment of glioma by oligodeoxynucleotide aptamer.

  4. A protein-targeting strategy used to develop a selective inhibitor of the E17K point mutation in the PH domain of Akt1

    Science.gov (United States)

    Deyle, Kaycie M.; Farrow, Blake; Qiao Hee, Ying; Work, Jeremy; Wong, Michelle; Lai, Bert; Umeda, Aiko; Millward, Steven W.; Nag, Arundhati; Das, Samir; Heath, James R.

    2015-05-01

    Ligands that can bind selectively to proteins with single amino-acid point mutations offer the potential to detect or treat an abnormal protein in the presence of the wild type (WT). However, it is difficult to develop a selective ligand if the point mutation is not associated with an addressable location, such as a binding pocket. Here we report an all-chemical synthetic epitope-targeting strategy that we used to discover a 5-mer peptide with selectivity for the E17K-transforming point mutation in the pleckstrin homology domain of the Akt1 oncoprotein. A fragment of Akt1 that contained the E17K mutation and an I19[propargylglycine] substitution was synthesized to form an addressable synthetic epitope. Azide-presenting peptides that clicked covalently onto this alkyne-presenting epitope were selected from a library using in situ screening. One peptide exhibits a 10:1 in vitro selectivity for the oncoprotein relative to the WT, with a similar selectivity in cells. This 5-mer peptide was expanded into a larger ligand that selectively blocks the E17K Akt1 interaction with its PIP3 (phosphatidylinositol (3,4,5)-trisphosphate) substrate.

  5. Determination of shell energies. Nuclear deformations and fission barriers

    International Nuclear Information System (INIS)

    Koura, Hiroyuki; Tachibana, Takahiro; Uno, Masahiro; Yamada, Masami.

    1996-01-01

    We have been studying a method of determining nuclear shell energies and incorporating them into a mass formula. The main feature of this method lies in estimating shell energies of deformed nuclei from spherical shell energies. We adopt three assumptions, from which the shell energy of a deformed nucleus is deduced to be a weighted sum of spherical shell energies of its neighboring nuclei. This shell energy should be called intrinsic shell energy since the average deformation energy also acts as an effective shell energy. The ground-state shell energy of a deformed nucleus and its equilibrium shape can be obtained by minimizing the sum of these two energies with respect to variation of deformation parameters. In addition, we investigate the existence of fission isomers for heavy nuclei with use of the obtained shell energies. (author)

  6. Seismic methodology in determining basis earthquake for nuclear installation

    International Nuclear Information System (INIS)

    Ameli Zamani, Sh.

    2008-01-01

    Design basis earthquake ground motions for nuclear installations should be determined to assure the design purpose of reactor safety: that reactors should be built and operated to pose no undue risk to public health and safety from earthquake and other hazards. Regarding the influence of seismic hazard to a site, large numbers of earthquake ground motions can be predicted considering possible variability among the source, path, and site parameters. However, seismic safety design using all predicted ground motions is practically impossible. In the determination of design basis earthquake ground motions it is therefore important to represent the influences of the large numbers of earthquake ground motions derived from the seismic ground motion prediction methods for the surrounding seismic sources. Viewing the relations between current design basis earthquake ground motion determination and modem earthquake ground motion estimation, a development of risk-informed design basis earthquake ground motion methodology is discussed for insight into the on going modernization of the Examination Guide for Seismic Design on NPP

  7. Determination of reservoir effective porosity using nuclear magnetic logging data

    International Nuclear Information System (INIS)

    Aksel'rod, S.M.; Danevich, V.I.; Sadykov, D.M.

    1979-01-01

    In connection with the development of nuclear magnetic logging (NML) the possibility has occurred to determine the effective porosity coefficient for rocks directly under the conditions of their occurrence. The initial amplitude of a signal of free precession of NML is proportional to the quantity of free fluid in the rock volume, which is determined by the index of free fluid (IFF). On the basis of the laboratory studies it is shown that the relation between IFF and free water content is always linear and doesn't depend on lithological characteristics of rocks, porous dimensions and distribution. Using this relation it's possible to estimate bound water content. While filling the reservoir with weakly mineralized water the IFF value coincides numerically with the effective porosity coefficient. Otherwise the content of hydrogen nuclei in a volume unit is much less; while calculating the effective porosity coefficient this fact is recorded by the index of the amplitude decrease which depends on temperature and increases with its growth (for oils). In strata containing intercalations of reservoirs and non-reservoirs the averaged according to stratum IFF value determines the mean-weighted values of effective porosity

  8. Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 1: Procedural overview

    International Nuclear Information System (INIS)

    2007-01-01

    Accurate determinations of volume are a fundamental component of any measurement-based system of control and accountability in a facility that processes or stores nuclear materials in liquid form. Volume determinations are typically made with the aid of a calibration or volume measurement equation that relates the response of the tank's measurement system to some independent measure of tank volume. The ultimate purpose of the calibration exercise is to estimate the tank's volume measurement equation (the inverse of the calibration equation), which relates tank volume to measurement system response. The steps carried out to acquire data for estimating the tank's calibration or volume measurement equation are collectively described as the process of tank calibration. This part of ISO 18213 describes procedures for tank calibration and volume determination for nuclear process tanks equipped with pressure-measurement systems for determining liquid content. Specifically, overall guidance is provided for planning a calibration exercise undertaken to obtain the data required for the measurement equation to estimate a tank's volume. The key steps in the procedure are also presented for subsequently using the estimated volume-measurement equation to determine tank liquid volumes. The procedures presented apply specifically to tanks equipped with bubbler probe systems for measuring liquid content. Moreover, these procedures produce reliable results only for clear (i.e. without suspended solids), homogeneous liquids that are at both thermal and static equilibrium. The paper elaborates on scope, physical principles involved, the calibration model, equipment required, a typical tank calibration procedure, calibration planning and pre-calibration activities, and volume determination. A bibliography is provided

  9. The Principal of International Nuclear Event Scale Determination and Its Implementation

    International Nuclear Information System (INIS)

    Piping Supriatna

    2006-01-01

    International Nuclear Event Scale (INES) is a scale system for determination nuclear event level on an international scale. Comprehension of INES system commonly as a way to motivate communication between nuclear management and the public, in accordance with disturbance to public safety level as the impact of nuclear installation accident. By using INES as the scaling system, the nuclear event is easy to be understood by nuclear group, journalist or by the public directly. In this report has been analyzed the procedure of nuclear event level determination refer to INES scaling system and its implementation in the field. In order to get same perception in determination of nuclear event level, it is necessary to improve full comprehension for INES and its implementation. (author)

  10. A nuclear data library for activity determinations of selected nuclides

    International Nuclear Information System (INIS)

    Baard, J.H.

    1991-11-01

    This report describes the GAMLIB 1-5 library, which is used in the calculation of the activity of radionuclides present in the gamma-ray spectra of irradiated neutron fluence detectors. The library contains all constants needed to calculate the activity for reactions normally applied in neutron fluence determinations, performed in irradiation experiments in the HFR. It also contains the nuclide constants for the activity calculation of gamma-ray measurements of U and Pu samples. The library consists of two kinds of tables, the first containing gamma-ray energies and gamma-ray emission probabilities with their uncertainties and the nuclide code, the other the nuclide code, decay constant, gamma -ray energies and gamma-ray emission probabilities. No cross-section data are stored in this library. All the relevant dat of the Nuclear Data Guide (Dordrecht, Kluwer 1989) have been used as base for this library. Other data have been obtained from recent literature. This library comprises 155 nuclides and 1115 gamma-ray energies. (author). 9 refs

  11. Factors determining the UK's back-end nuclear fuel cycle strategy and future nuclear systems

    International Nuclear Information System (INIS)

    Dunn, M.J.; Ainsworth, Z.E.

    2002-01-01

    Nuclear generating capacity in the UK is static with no units currently under construction. The AGRs and the UK's only PWR, Sizewell B, are operated by British Energy Generation Ltd (BEGL) and British Energy Generation (UK) Ltd (BEG(UK)L), who are subsidiaries of British Energy plc (BE) which was privatised in July 1996. Ownership of the Magnox stations, which were excluded from this privatisation, has now been transferred to BNFL.Government policy on spent fuel management in the UK is that it is for the owners of the spent fuel to decide on the appropriate spent fuel management options, based on their own commercial judgement, subject to meeting the necessary regulatory requirements. The main factors which have predominantly determined UK utility decisions on spent fuel management, to date, have been based on the technical considerations of the spent fuel characteristics, economic attractiveness of the options and at reactor site spent fuel storage capacities. To date, reprocessing has been the dominant form of spent fuel treatment in the UK. Spent fuel storage facilities consist of a mixture of at-reactor stores and large, centralised ponds associated with the reprocessing activities which take place at the Sellafield site. BEGL and BEG(UK)L have contracts for the lifetime arisings of AGR fuel which allow for all AGR spent fuel to be sent to Sellafield for reprocessing or long-term storage. The prompt reprocessing of all Magnox fuel will continue, and spent PWR fuel will continue to be stored at the reactor site in the short to medium term. It is likely that a combination of factors, which are discussed later in this paper, will continue to affect back-end nuclear fuel cycle strategy and future nuclear systems. (author)

  12. miR-25-3p, Positively Regulated by Transcription Factor AP-2α, Regulates the Metabolism of C2C12 Cells by Targeting Akt1

    Directory of Open Access Journals (Sweden)

    Feng Zhang

    2018-03-01

    Full Text Available miR-25, a member of the miR-106b-25 cluster, has been reported as playing an important role in many biological processes by numerous studies, while the role of miR-25 in metabolism and its transcriptional regulation mechanism remain unclear. In this study, gain-of-function and loss-of-function assays demonstrated that miR-25-3p positively regulated the metabolism of C2C12 cells by attenuating phosphoinositide 3-kinase (PI3K gene expression and triglyceride (TG content, and enhancing the content of adenosine triphosphate (ATP and reactive oxygen species (ROS. Furthermore, the results from bioinformatics analysis, dual luciferase assay, site-directed mutagenesis, qRT-PCR, and Western blotting demonstrated that miR-25-3p directly targeted the AKT serine/threonine kinase 1 (Akt1 3′ untranslated region (3′UTR. The core promoter of miR-25-3p was identified, and the transcription factor activator protein-2α (AP-2α significantly increased the expression of mature miR-25-3p by binding to its core promoter in vivo, as indicated by the chromatin immunoprecipitation (ChIP assay, and AP-2α binding also downregulated the expression of Akt1. Taken together, our findings suggest that miR-25-3p, positively regulated by the transcription factor AP-2α, enhances C2C12 cell metabolism by targeting the Akt1 gene.

  13. Altered AKT1 and MAPK1 Gene Expression on Peripheral Blood Mononuclear Cells and Correlation with T-Helper-Transcription Factors in Systemic Lupus Erythematosus Patients

    Directory of Open Access Journals (Sweden)

    Sonia Garcia-Rodriguez

    2012-01-01

    Full Text Available Kinases have been implicated in the immunopathological mechanisms of Systemic Lupus Erythematosus (SLE. v-akt murine-thymoma viral-oncogene-homolog 1 (AKT1 and mitogen-activated-protein-kinase 1 (MAPK1 gene expressions in peripheral mononuclear cells from thirteen SLE patients with inactive or mild disease were evaluated using quantitative real-time reverse-transcription polymerase-chain-reaction and analyzed whether there was any correlation with T-helper (Th transcription factors (TF gene expression, cytokines, and S100A8/S100A9-(Calprotectin. Age- and gender-matched thirteen healthy controls were examined. AKT1 and MAPK1 expressions were upregulated in SLE patients and correlated with Th17-(Retinoic acid-related orphan receptor (ROR-C, T-regulatory-(Treg-(Transforming Growth Factor Beta (TGFB-2, and Th2-(interleukin (IL-5-related genes. MAPK1 expression correlated with Th1-(IL-12A, T-box TF-(T-bet, Th2-(GATA binding protein-(GATA-3, and IL-10 expressions. IL-10 expression was increased and correlated with plasma Tumor Necrosis Factor (TNF-α and Th0-(IL-2, Th1-(IL-12A, T-bet, GATA3, Treg-(Forkhead/winged-helix transcription factor- (FOXP-3, and IL-6 expressions. FOXP3 expression, FOXP3/RORC, and FOXP3/GATA3 expression ratios were increased. Plasma IL-1β, IL-12(p70, Interferon-(IFN-γ, and IL-6 cytokines were augmented. Plasma IL-1β, IL-6, IL-2, IFN-γ, TNF-α, IL-10, and IL-13 correlated with C-reactive protein, respectively. Increased Calprotectin correlated with neutrophils. Conclusion, SLE patients presented a systemic immunoinflammatory activity, augmented AKT1 and MAPK1 expressions, proinflammatory cytokines, and Calprotectin, together with increased expression of Treg-related genes, suggesting a regulatory feedback opposing the inflammatory activity.

  14. GRP1 PH Domain, Like AKT1 PH Domain, Possesses a Sentry Glutamate Residue Essential for Specific Targeting to Plasma Membrane PI(3,4,5)P3

    Science.gov (United States)

    Pilling, Carissa; Landgraf, Kyle E.; Falke, Joseph J.

    2011-01-01

    During the appearance of the signaling lipid PI(3,4,5)P3, an important subset of pleckstrin homology (PH) domains target signaling proteins to the plasma membrane. To ensure proper pathway regulation, such PI(3,4,5)P3-specific PH domains must exclude the more prevalant, constitutive plasma membrane lipid PI(4,5)P2 and bind the rare PI(3,4,5)P3 target lipid with sufficiently high affinity. Our previous study of the E17K mutant of protein kinase B (AKT1) PH domain, together with evidence from Carpten et al (1), revealed that the native AKT1 E17 residue serves as a sentry glutamate that excludes PI(4,5)P2, thereby playing an essential role in specific PI(3,4,5)P3 targeting (2). The sentry glutamate hypothesis proposes that an analogous sentry glutamate residue is a widespread feature of PI(3,4,5)P3-specific PH domains, and that charge reversal mutation at the sentry glutamate position will yield both increased PI(4,5)P2 affinity and constitutive plasma membrane targeting. To test this hypothesis the present study investigates the E345 residue, a putative sentry glutamate, of General Receptor for Phosphoinositides 1 (GRP1) PH domain. The results show that incorporation of the E345K charge reversal mutation into GRP1 PH domain enhances PI(4,5)P2 affinity 8-fold and yields constitutive plasma membrane targeting in cells, reminiscent of the effects of the E17K mutation in AKT1 PH domain. Hydrolysis of plasma membrane PI(4,5)P2 releases E345K GRP1 PH domain into the cytoplasm and the efficiency of this release increases when target Arf6 binding is disrupted. Overall, the findings provide strong support for the sentry glutamate hypothesis and suggest that the GRP1 E345K mutation will be linked to changes in cell physiology and human pathologies, as demonstrated for AKT1 E17K (1, 3). Analysis of available PH domain structures suggests that a lone glutamate residue (or, in some cases an aspartate) is a common, perhaps ubiquitous, feature of PI(3,4,5)P3-specific binding

  15. Determination Public Acceptance Segmentation for Nuclear Power Program Interest

    International Nuclear Information System (INIS)

    Syirrazie Che Soh; Aini Wahidah Abdul Wahab

    2012-01-01

    This paper is focus to discuss segmentation aspect among inter-disciplinary group of public. This discussion is the pre-stage to ensure the right initiative strategies are implemented to gain public interest and acceptance towards on developing nuclear power plant. The applied strategies are implemented based on different interest among the different groups of public. These strategies may increase public acceptance level towards developing nuclear power plant. (author)

  16. Wnt1 Neuroprotection Translates into Improved Neurological Function during Oxidant Stress and Cerebral Ischemia Through AKT1 and Mitochondrial Apoptotic Pathways

    Directory of Open Access Journals (Sweden)

    Zhao Zhong Chong

    2010-01-01

    Full Text Available Although essential for the development of the nervous system, Wnt1 also has been associated with neurodegenerative disease and cognitive loss during periods of oxidative stress. Here we show that endogenous expression of Wnt1 is suppressed during oxidative stress in both in vitro and in vivo experimental models. Loss of endogenous Wnt1 signaling directly correlates with neuronal demise and increased functional deficit, illustrating that endogenous neuronal Wnt1 offers a vital level of intrinsic cellular protection against oxidative stress. Furthermore, transient overexpression of Wnt1 or application of exogenous Wnt1 recombinant protein is necessary to preserve neurological function and rescue neurons from apoptotic membrane phosphatidylserine externalization and genomic DNA degradation, since blockade of Wnt1 signaling with a Wnt1 antibody or dickkopf related protein 1 abrogates neuronal protection by Wnt1. Wnt1 ultimately relies upon the activation of Akt1, the modulation of mitochondrial membrane permeability, and the release of cytochrome c to control the apoptotic cascade, since inhibition of Wnt1 signaling, the phosphatidylinositol 3-kinase pathway, or Akt1 activity abrogates the ability of Wnt1 to block these apoptotic components. Our work identifies Wnt1 and its downstream signaling as cellular targets with high clinical potential for novel treatment strategies for multiple disorders precipitated by oxidative stress.

  17. Observation of rotating nuclear molecules and determination of their lifetimes

    Energy Technology Data Exchange (ETDEWEB)

    Comas, V.; Heinz, S.; Ackermann, D.; Heredia, J.; Hessberger, F.P.; Khuyagbaatar, J.; Kindler, B.; Lommel, B.; Mann, R. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany); Hofmann, S. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany); Goethe-Universitaet Frankfurt, Institut fuer Physik, Frankfurt (Germany)

    2012-12-15

    Long-living rotating nuclear molecules (or ''dinuclear systems'') have been observed at the velocity filter SHIP at GSI in reactions of {sup 64}Ni + {sup 207}Pb at Coulomb barrier energies. The rotation was directly revealed by the velocity spectra of deep inelastic target-like transfer products which are formed during the lifetime of the nuclear molecule and emitted after its breakup. The corresponding rotation angles were about 180 degree pointing to long nuclear interaction times or lifetimes of the system, respectively. We deduced the lifetimes from the lines in the velocity spectra originating from two different rotation angles. Further, the unambiguous correlation of a certain transfer product with its individual velocity spectrum allowed us to study the lifetimes as a function of the number of transferred protons. (orig.)

  18. Enabling legislation and regulatory determinations for a nuclear power programme

    International Nuclear Information System (INIS)

    Ha-Vinh, Phuong

    1975-01-01

    Broad definition of the scope of enabling legislation, identification of branches of laws involved in the licensing and regulatory control, overview of some typical licensing practices and provisions, some specific legislative or regulatory requirements including financial security to over nuclear liability. (HP) [de

  19. Determination of nuclear-matter temperature and density

    International Nuclear Information System (INIS)

    Wolf, K.L.

    1980-01-01

    Some of the things learned about nuclear matter under extreme conditions during the past few years in relativistic heavy ion studies are reviewed. Two developments are discussed. The completion of analyses and publication of results from the impact parameter selected, single-particle inclusive experiments have proven to be important. Preliminary results from the new generation of two-particle correlation and particle-exclusive measurements, especially those using streamer chambers, look even more definitive. Also the measurement of more exotic ejectiles with long mean free paths in nuclear matter promises to provide more basic information. Calculations are offering real guidance and are providing explanations of high energy collisions. The Monte Carlo and intranuclear cascade calculations discussed are especially informative

  20. Multiaxial Polarity Determines Individual Cellular and Nuclear Chirality.

    Science.gov (United States)

    Raymond, Michael J; Ray, Poulomi; Kaur, Gurleen; Fredericks, Michael; Singh, Ajay V; Wan, Leo Q

    2017-02-01

    Intrinsic cell chirality has been implicated in the left-right (LR) asymmetry of embryonic development. Impaired cell chirality could lead to severe birth defects in laterality. Previously, we detected cell chirality with an in vitro micropatterning system. Here, we demonstrate for the first time that chirality can be quantified as the coordination of multiaxial polarization of individual cells and nuclei. Using an object labeling, connected component based method, we characterized cell chirality based on cell and nuclear shape polarization and nuclear positioning of each cell in multicellular patterns of epithelial cells. We found that the cells adopted a LR bias the boundaries by positioning the sharp end towards the leading edge and leaving the nucleus at the rear. This behavior is consistent with the directional migration observed previously on the boundary of micropatterns. Although the nucleus is chirally aligned, it is not strongly biased towards or away from the boundary. As the result of the rear positioning of nuclei, the nuclear positioning has an opposite chirality to that of cell alignment. Overall, our results have revealed deep insights of chiral morphogenesis as the coordination of multiaxial polarization at the cellular and subcellular levels.

  1. The determination of trainee teachers' conceptual frameworks about nuclear energy and environment

    Energy Technology Data Exchange (ETDEWEB)

    Aladag, C [Department of Geography, Faculty of Educational, University of Necmettin Erbakan, Kenya (Turkey)

    2013-07-01

    The aim of this study is to reveal the cognitive construction about the relationship between nuclear energy and environment of the undergraduates who have studied science of environment by using word association test and to determine the conception mistakes. The research was made on 81 trainee teachers who study at Ahmet Kelerlu Faculty of Education Department of Geography and Biology, University of Necmettin Erbakan on 2012-2013 academic year fall semester. In the study, it was seen that the topics which the undergraduates mostly refer in their written statements were the nuclear energy's indication of improvement of countries, its necessity, nuclear accidents, nuclear weapons and the ecocide. The other opinions which gained importance were nuclear reaction, nuclear raw material and countries producing nuclear energy. It's seen that nuclear accidents and nuclear weapons are very effective on the graduates' point of view. The opinions about nuclear energy's harm to the environment show that environmental awareness became of secondary importance. The written concepts about these two opinions are very close to each other by percentage. Mainly, the radiation effects caused by the nuclear accidents constitute the fundamental point of undergraduates' perception of environment. (author)

  2. Review of fracture properties of nuclear materials determined by Hertzian indentation

    International Nuclear Information System (INIS)

    Routbort, J.; Matzke, H.

    1985-01-01

    A brief description of the determination of the surface fracture energy and the fracture toughness from a Hertzian indentation test is given. A number of theoretical and experimental problems are discussed. Results obtained on a variety of nuclear fuels and nuclear-waste-containment materials are reviewed and compared with values measured by other techniques. The Hertzian indentation test yields reliable fracture parameters

  3. Ab initio determination of the nuclear quadrupole moments of 114In, 115In, and 117In

    International Nuclear Information System (INIS)

    Errico, Leonardo A.; Renteria, Mario

    2006-01-01

    We present here ab initio determinations of the nuclear-quadrupole moment Q of hyperfine-probe-nuclear states of three different In isotopes: the 5 + 192 keV excited state of 114 In (probe for nuclear quadrupole alignment spectroscopy), the 9/2 + ground state of 115 In (nuclear magnetic and nuclear quadrupole resonance probe), and the 3/2 + 659 keV excited state of 117 In (perturbed angular correlations probe). These nuclear-quadrupole moments were determined by comparing experimental nuclear-quadrupole frequencies to the electric field gradient tensor calculated with high accuracy at In sites in metallic indium within the density functional theory. These ab initio calculations were performed with the full-potential linearized augmented plane wave method. The results obtained for the quadrupole moments of 114 In [Q( 114 In)=-0.14(1) b] are in clear discrepancy with those reported in the literature [Q( 114 In)=+0.16(6) b and +0.739(12) b]. For 115 In and 117 In our results are in excellent agreement with the literature and in the last case Q( 117 In) is determined with more precision. In the case of Q( 117 In), its sign cannot be determined because standard γ-γ perturbed angular correlations experiments are not sensitive to the sign of the nuclear-quadrupole frequency

  4. Nuclear medical determination of left ventricular diastolic function in coronary heart disease

    International Nuclear Information System (INIS)

    Brugger, P.; Laesser, W.K.; Kullich, W.; Stoiberer, I.; Klein, G.

    1985-01-01

    In 64 patients with coronary heart disease, the left ventricular diastolic function was determined by means of a new nuclear medical method (nuclear stethoscope). The investigations revealed an abnormal diastolic filling in 85.9% of the cases on the basis of the parameters peak filling rate and time to peak filling rate as manifestation of a disturbed ventricular function

  5. Determination of radionuclides. Fingerprint determination on protection clothing from the controlled areas in nuclear facilities

    International Nuclear Information System (INIS)

    Scholand, Soeren

    2014-01-01

    ENS (Euro Nuclear Services) in Coevorden, Netherlands, is decontaminating und providing protection clothing for the personnel in nuclear facilities. The capacity of the laundry is about 750 kg/h. The clean laundry section is cleaning non-contaminated or very low contaminated articles, i.e. socks or underwear. Fingerprint is defined as the activity of certain radionuclides that differs in the different nuclear facilities. For the reception inspection the dose rate measured with scintillation detectors is compared with the customer specific fingerprint. The total activity is usually 2000 Bq/g. The dose rate limit is 0.3 mSv/h.

  6. Nuclear medical methods for determination of bone mineral content

    International Nuclear Information System (INIS)

    Fischer, M.; Kempers, B.; Tschepke, H.D.; Spitz, J.

    1988-01-01

    Osteoporosis is becoming recognized as a major social and economical health problem. Bone mineral content (BMC) depends on many hormonal and metabolic factors. The pathophysiological mechanism of the loss of bone mass is still unclear. For preventive diagnosis and treatment of osteoporosis, quantitative technology is required that will measure BMC with high precision and reproducibility. Nuclear medical methods permit the BMC of the appendicular skeleton to be measured by single photon absorptiometry. Whole-body BMC, as well as spine and femur BMC, can be measured by dual photon absorptiometry. The results from both procedures are reasonably precise and correlate well with the ash weight of isolated bone. The radiation exposure level in both SPA and DPA is low. SPA and DPA may be used for cost-effective screening of high-risk patients to predict the likelihood of future fractures and control osteoporosis therapy. (orig.) [de

  7. Determining phenols in coal conversion products by nuclear magnetic resonance

    Energy Technology Data Exchange (ETDEWEB)

    Kanitskaya, L.V.; Kushnarev, D.F.; Polonov, V.M.; Kalabin, G.A.

    1985-03-01

    Possibility of using nuclear magnetic resonance spectra of the hydrogen 1 (/sup 1/H) isotope for a qualitative and quantitative evaluation of the hydroxyl groups in the products of coal processing is investigated. The basis of the method is the fact that in NMR spectra of the /sup 1/H in organic compounds with acid protons, the latter are unprotected when strong bases are used as solvents because of intermolecular hydrogen bonds. The resin from the medium-temperature semicoking of Cheremkhovskii coals, its hydrogenate, and phenol fraction of the hydrogenate were used for the investigation. The results were compared with the results of other NMR spectroscopy methods. The high solubility of hexamethanol and the fact that the products can be analyzed in the natural state, are some advantages of the method. 18 references.

  8. Nuclear parameters determination of the 127Te β - decay: a proposal for teaching nuclear physics

    International Nuclear Information System (INIS)

    Batista, Wagner Fonseca

    2011-01-01

    A study of the 127 Te β - decay was carried out by means of gamma spectroscopy measurements using high resolution HPGe detector, in the region from 30 keV to 1.0 MeV, aiming to get a better understanding of the 127 Te nuclear structure. The radioactive sources of 12 7Te were obtained from the 126 Te(n,γ) 1 '2 7 Te nuclear reaction produced in the IEA- R1 nuclear reactor at IPEN/CNEN-SP. Five gamma t ransitions previously attributed to this decay were confirmed with a better precision than previously. The half-life of 127 Te was also studied resulting in data with lower uncertainty. Using a set of data selected from gamma spectroscopy measurements was developed and applied a didactic proposal for high school students using the Excel software. (author)

  9. Various methods for determination of liquid viscosity with nuclear track membranes

    International Nuclear Information System (INIS)

    Guo Shilun

    1991-01-01

    A systematic study has been performed of the methods for determination of liquid viscosity with nuclear track membranes. Absolute and relative measurements have been suggested, the latter including relative measurements of absolute viscosity and kinematic viscosity. The study shows that the nuclear track membrane is a unique element for determination of liquid viscosity because it is small in volume, accurate in results and easy to manipulate in industries and laboratories

  10. Density determination of sintered ceramic nuclear fuel materials

    International Nuclear Information System (INIS)

    Landspersky, H.; Medek, J.

    1980-01-01

    The feasibility was tested of using solids for pycnometric determination of the density of uranium dioxide-based sintered ceramic fuel materials manufactured by the sol-gel method in the shape of spherical particles of 0.7 to 1.0 mm in size and of particles smaller than 200 μm. For fine particles, this is the only usable method of determining their density which is a very important parameter of the fine fraction when it is employed for the manufacture of fuel elements by vibration compacting. The method consists in compacting a mixture of pycnometric material and dispersed particles of uranium dioxide, determining the size and weight of the compact, and in calculating the density of the material measured from the weight of the oxide sample in the mixture. (author)

  11. A review of flow analysis methods for determination of radionuclides in nuclear wastes and nuclear reactor coolants.

    Science.gov (United States)

    Trojanowicz, Marek; Kołacińska, Kamila; Grate, Jay W

    2018-06-01

    The safety and security of nuclear power plant operations depend on the application of the most appropriate techniques and methods of chemical analysis, where modern flow analysis methods prevail. Nevertheless, the current status of the development of these methods is more limited than it might be expected based on their genuine advantages. The main aim of this paper is to review the automated flow analysis procedures developed with various detection methods for the nuclear energy industry. The flow analysis methods for the determination of radionuclides, that have been reported to date, are primarily focused on their environmental applications. The benefits of the application of flow methods in both monitoring of the nuclear wastes and process analysis of the primary circuit coolants of light water nuclear reactors will also be discussed. The application of either continuous flow methods (CFA) or injection methods (FIA, SIA) of the flow analysis with the β-radiometric detection shortens the analysis time and improves the precision of determination due to mechanization of certain time-consuming operations of the sample processing. Compared to the radiometric detection, the mass spectrometry (MS) detection enables one to perform multicomponent analyses as well as the determination of transuranic isotopes with much better limits of detection. Copyright © 2018 Elsevier B.V. All rights reserved.

  12. Determining the efficacy of nuclear security through computer simulation

    Energy Technology Data Exchange (ETDEWEB)

    Chornobo, N.; Waller, E., E-mail: nicholas.chornoboy@uoit.ca [University of Ontario Institute of Technology, Oshawa, ON (Canada)

    2015-07-01

    Currently when creating new security regimes or analyzing current ones it is difficult to determine how effective they are or will be. This leads to many decisions being made using subjective expert opinion or expensive live exercises. While these are useful for determining the effectiveness it would be ideal to have an easy way to simulate and attack through software in order to allow rapid testing of many different scenarios simply. This work focuses on modifying the force on force simulator stage to run these kinds of tests. (author)

  13. Determination of uranium traces in fuel cans of nuclear reactors

    International Nuclear Information System (INIS)

    Acosta L, C.E.; Benavides M, A.M.; Sanchez P, L.A.; Nava S, G.F.

    1997-01-01

    The objective of this work is to quantify the uranium content that as impurity can be found in zircon and zircaloy alloys which are used in the construction of fuel cans. The determination of this serves as a quality control measure due to that the increment of uranium content in alloy, diminishing the corrosion resistance. The fluorimetric method was used to do this determination. It is a very sensitive, reliable, rapid method also high reproducibility and repeatability as well as low detection limits (0.25 mg/kg). (Author)

  14. Nuclear determination of saturation profiles in core plugs

    International Nuclear Information System (INIS)

    Sletsgaard, J.; Oelgaard, P.L.

    1997-01-01

    A method to determine liquid saturations in core plugs during flooding is of importance when the relative permeability and capillary pressure function are to be determined. This part of the EFP-95 project uses transmission of γ-radiation to determine these saturations. In γ-transmission measurements, the electron density of the given substance is measured. This is an advantage as compared to methods that use electric conductivity, since neither oil nor gas conducts electricity. At the moment a single 137 Cs-source is used, but a theoretical investigation of whether it is possible to determine three saturations, using two radioactive sources with different γ-energies, has been performed. Measurements were made on three core plugs. To make sure that the measurements could be reproduced, all the plugs had a point of reference, i.e. a mark so that it was possible to place the plug same way every time. Two computer programs for calculation of saturation and porosity and the experimental setup are listed. (EG)

  15. Spectrographic determination of lithium in nuclear grade calcium

    International Nuclear Information System (INIS)

    Artaud, J.; Cittanova, J.

    1957-01-01

    A method is described for the spectrographic determination of lithium in calcium. The samples are converted directly to CaCO 3 . A method of fractional distillation in the arc, using KCl as carrier, makes it possible to detect and measure the Li content to 0,1 ppm. (author) [fr

  16. Determination of 237Np in environmental and nuclear samples: A review of the analytical method

    International Nuclear Information System (INIS)

    Thakur, P.; Mulholland, G.P.

    2012-01-01

    A number of analytical methods has been developed and used for the determination of neptunium in environmental and nuclear fuel samples using alpha, ICP–MS spectrometry, and other analytical techniques. This review summarizes and discusses development of the radiochemical procedures for separation of neptunium (Np), since the beginning of the nuclear industry, followed by a more detailed discussion on recent trends in the separation of neptunium. This article also highlights the progress in analytical methods and issues associated with the determination of neptunium in environmental samples. - Highlights: ► Determination of Np in environmental and nuclear samples is reviewed. ► Various analytical methods used for the determination of Np are listed. ► Progress and issues associated with the determination of Np are discussed.

  17. Determination of iron 55 in nuclear wastes and effluents

    International Nuclear Information System (INIS)

    Raymond, A.; Revy, D.

    1989-01-01

    The methods for iron 55 analysis, described in this report allows measurement in different types of radioactive wastes after a specific chemical separation. Detection limit is near 1 Bq/l and the concentration factor can reach 100. Activity level found show that iron 55 is a major activation product, then the chemical determination is indispensable for a complete inventory of radionuclides in radioactive wastes [fr

  18. Nuclear equipment to determine soil and water mass attenuation coefficients

    International Nuclear Information System (INIS)

    Zucchi, O.L.A.D.; Nascimento Filho, V.F. do

    1984-01-01

    The feasibility of substituting the monochannel gamma spectrometer, traditionally used in the gamma ray attenuation technique, for a less sophisticated and less expensive system of integral counting is studied. The proposed system can be operated by a non-specialized person. Three detection systems were used in the determination of the mass attenuation coefficients for different types of soil and for water. (M.A.C.) [pt

  19. Determination of nuclear tracks parameters on sequentially etched PADC detectors

    Science.gov (United States)

    Horwacik, Tomasz; Bilski, Pawel; Koerner, Christine; Facius, Rainer; Berger, Thomas; Nowak, Tomasz; Reitz, Guenther; Olko, Pawel

    Polyallyl Diglycol Carbonate (PADC) detectors find many applications in radiation protection. One of them is the cosmic radiation dosimetry, where PADC detectors measure the linear energy transfer (LET) spectra of charged particles (from protons to heavy ions), supplementing TLD detectors in the role of passive dosemeter. Calibration exposures to ions of known LET are required to establish a relation between parameters of track observed on the detector and LET of particle creating this track. PADC TASTRAK nuclear track detectors were exposed to 12 C and 56 Fe ions of LET in H2 O between 10 and 544 keV/µm. The exposures took place at the Heavy Ion Medical Accelerator (HIMAC) in Chiba, Japan in the frame of the HIMAC research project "Space Radiation Dosimetry-Ground Based Verification of the MATROSHKA Facility" (20P-240). Detectors were etched in water solution of NaOH with three different temperatures and for various etching times to observe the appearance of etched tracks, the evolution of their parameters and the stability of the etching process. The applied etching times (and the solution's concentrations and temperatures) were: 48, 72, 96, 120 hours (6.25 N NaOH, 50 O C), 20, 40, 60, 80 hours (6.25 N NaOH, 60 O C) and 8, 12, 16, 20 hours (7N NaOH, 70 O C). The analysis of the detectors involved planimetric (2D) measurements of tracks' entrance ellipses and mechanical measurements of bulk layer thickness. Further track parameters, like angle of incidence, track length and etch rate ratio were then calculated. For certain tracks, results of planimetric measurements and calculations were also compared with results of optical track profile (3D) measurements, where not only the track's entrance ellipse but also the location of the track's tip could be directly measured. All these measurements have been performed with the 2D/3D measurement system at DLR. The collected data allow to create sets of V(LET in H2 O) calibration curves suitable for short, intermediate and

  20. ANL calculational methodologies for determining spent nuclear fuel source term

    International Nuclear Information System (INIS)

    McKnight, R. D.

    2000-01-01

    Over the last decade Argonne National Laboratory has developed reactor depletion methods and models to determine radionuclide inventories of irradiated EBR-II fuels. Predicted masses based on these calculational methodologies have been validated using available data from destructive measurements--first from measurements of lead EBR-II experimental test assemblies and later using data obtained from processing irradiated EBR-II fuel assemblies in the Fuel Conditioning Facility. Details of these generic methodologies are described herein. Validation results demonstrate these methods meet the FCF operations and material control and accountancy requirements

  1. Determination of the fission coefficients in thermal nuclear reactors for antineutrino detection

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Lenilson M. [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Cabral, Ronaldo G., E-mail: rgcabral@ime.eb.b [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil); Anjos, Joao C.C. dos, E-mail: janjos@cbpf.b [Centro Brasileiro de Pesquisas Fisicas (CBPF), Rio de Janeiro, RJ (Brazil). Dept. GLN - G

    2011-07-01

    The nuclear reactors in operation periodically need to change their fuel. It is during this process that these reactors are more vulnerable to occurring of several situations of fuel diversion, thus the monitoring of the nuclear installations is indispensable to avoid events of this nature. Considering this fact, the most promissory technique to be used for the nuclear safeguard for the nonproliferation of nuclear weapons, it is based on the detection and spectroscopy of antineutrino from fissions that occur in the nuclear reactors. The detection and spectroscopy of antineutrino, they both depend on the single contribution for the total number of fission of each actinide in the core reactor, these contributions receive the name of fission coefficients. The goal of this research is to show the computational and mathematical modeling used to determinate these coefficients for PWR reactors. (author)

  2. Determination of B and Li in nuclear materials by secondary-ion mass spectrometry

    International Nuclear Information System (INIS)

    Eby, R.E.; Christie, W.H.

    1981-01-01

    Secondary ion mass spectrometry (SIMS) was used to perform mass and isotopic analysis for B and Li in samples that are not readily amenable to more conventional mass spectrometric techniques (e.g., surface ionization, electron impact, etc.). In this paper three specific applications of SIMS analysis to nuclear materials are discussed: first, the quantitative determination of B and its isotopic composition in borosilicate glasses; second, the determination of the isotopic composition of B and Li in irradiated nuclear-grade aluminum oxide/boron carbide composite pellets, and, lastly, the quantitative and isotopic determination of B and Li in highly radioactive solutions of unknown composition

  3. Sequential determination of important ecotoxic radionuclides in nuclear waste samples

    International Nuclear Information System (INIS)

    Bilohuscin, J.

    2016-01-01

    In the dissertation thesis we focused on the development and optimization of a sequential determination method for radionuclides 93 Zr, 94 Nb, 99 Tc and 126 Sn, employing extraction chromatography sorbents TEVA (R) Resin and Anion Exchange Resin, supplied by Eichrom Industries. Prior to the attestation of sequential separation of these proposed radionuclides from radioactive waste samples, a unique sequential procedure of 90 Sr, 239 Pu, 241 Am separation from urine matrices was tried, using molecular recognition sorbents of AnaLig (R) series and extraction chromatography sorbent DGA (R) Resin. On these experiments, four various sorbents were continually used for separation, including PreFilter Resin sorbent, which removes interfering organic materials present in raw urine. After the acquisition of positive results of this sequential procedure followed experiments with a 126 Sn separation using TEVA (R) Resin and Anion Exchange Resin sorbents. Radiochemical recoveries obtained from samples of radioactive evaporate concentrates and sludge showed high efficiency of the separation, while values of 126 Sn were under the minimum detectable activities MDA. Activity of 126 Sn was determined after ingrowth of daughter nuclide 126m Sb on HPGe gamma detector, with minimal contamination of gamma interfering radionuclides with decontamination factors (D f ) higher then 1400 for 60 Co and 47000 for 137 Cs. Based on the acquired experiments and results of these separation procedures, a complex method of sequential separation of 93 Zr, 94 Nb, 99 Tc and 126 Sn was proposed, which included optimization steps similar to those used in previous parts of the dissertation work. Application of the sequential separation method for sorbents TEVA (R) Resin and Anion Exchange Resin on real samples of radioactive wastes provided satisfactory results and an economical, time sparing, efficient method. (author)

  4. Isotopic Determination of Nuclear Materials Using Nuclear Fission Track Registration Technique and Thermal Ionization Mass Spectrometric Technique

    International Nuclear Information System (INIS)

    Jeon, Young Sin; Pyo, Hyeong Yeol; Park, Yong Joon; Song, Kyu Seok; Kim, Won Ho; Jee, Kwang Yong

    2007-05-01

    It is very important to develope the technology for the determination of isotopic ratios of hot particles( 234 U, 235 U, 236 U etc.) detected from swipe samples of various nuclear facilities. This technology is highly competitive internationally and has to be established independently as long as our government maintains atomic energy and treats nuclear materials. In this text, sample pretreatment procedure, gamma-ray counting, alpha or fission track techniques, isotopic analysis of U and Pu, background problems and detection limits for mass determination, and their application to the real swipe sample were described with detailed procedure. This technology would contribute to the Korean economy's high growth rate as well as to superiority of government's leading research and development programs if successfully established

  5. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Alvarez, A.; Correa, E.; Navarro, N.; Sancho, C.; Angeles, A.

    2000-01-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  6. Determination of leveled costs of electric generation for gas plants, coal and nuclear

    International Nuclear Information System (INIS)

    Alonso V, G.; Palacios H, J.C.; Ramirez S, J.R.; Gomez, A.

    2005-01-01

    The present work analyzes the leveled costs of electric generation for different types of nuclear reactors known as Generation III, these costs are compared with the leveled costs of electric generation of plants with the help of natural gas and coal. In the study several discount rates were used to determine their impact in the initial investment. The obtained results are comparable with similar studies and they show that it has more than enough the base of the leveled cost the nuclear option it is quite competitive in Mexico. Also in this study it is also thinks about the economic viability of a new nuclear power station in Mexico. (Author)

  7. Determination of nuclear quadrupole moments – An example of the synergy of ab initio calculations and microwave spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Kellö, Vladimir [Department of Physical Chemistry, Comenius University, SK-842 15 Bratislava (Slovakia)

    2015-01-22

    Highly correlated scalar relativistic calculations of electric field gradients at nuclei in diatomic molecules in combination with accurate nuclear quadrupole coupling constants obtained from microwave spectroscopy are used for determination of nuclear quadrupole moments.

  8. Determination of the probability of an aircraft falling on a nuclear power plant

    International Nuclear Information System (INIS)

    Kostikov, V.A.; Smol'nikov, V.L.; Baranaev, Yu.D.; Viktorov, A.N.; Vladykov, G.M.; Dolgov, V.V.; Shvedenko, I.M.

    1993-01-01

    Significant possible external actions at nuclear power plants are events associated with aviation accidents, in which, for one reason or another, an airplane or a fragment of an airplane can fall on the building and destroy the reactor or important safety systems. Measures for preventing an aircraft from striking a nuclear power plant include flight limitations and siting of airports, and flight corridors are created near nuclear power plants. The reactor itself can be placed in a special strong protective envelope. The specific technical measures are determined, to a significant degree, by the type of accident and the type of aircraft. It is now acknowledged, including in documents published by the IAEA, that assessment of the adequacy of measures for protecting a nuclear power plant from aircraft is most efficiently done by means of a probability analysis. We expound below briefly the methodology and the results obtained by its application to the South Ural nuclear power plant and the Bilibinskaya nuclear heat and electricity station. Falling of an aircraft (jet or helicopter) on a nuclear power plant is an extreme event, whose probability is determined mainly by flight safety measures, the intensity of flights in the region, and the distribution of aviation accidents by type and characteristic consequences. Flight safety is determined by the frequency with which aviation accidents occur per hour of flight and mainly depends on the sophistication of the aviation technology. The intensity of flights near a nuclear power plant is estimated taking into account the administrative and organizational measures for limiting flights and is a characteristic of the region where the power plant is located, as is the distribution of aviation accidents by type

  9. Nuclear techniques for the determination of protein content in plant material

    International Nuclear Information System (INIS)

    Niemann, E.G.

    1980-01-01

    Elemental analysis for nitrogen has gained in importance over the last decade, as protein improvement and protein control in food and feed has come to be recognized as one of the most promising ways of overcoming deficiencies in food production and distribution. The need for fast and reliable screening methods has stimulated the improvement and automation of classic chemical methods for protein and nitrogen determination and, on the other hand, the development and adaptation of physical and nuclear analysis procedures. After about ten years of work this process has come to a stage where a critical evaluation of the existing methods seems necessary and justified. The present review describes and compares nuclear techniques for nitrogen determination in plant material. These include activation analysis techniques, based on various nuclear reactions, initiated by fast and thermal neutrons, energetic photons, protons, deuterons and α-particles. Other nuclear methods have been applied for nitrogen or protein determination, like ESCA, PIXE, NMR, NQR and Moessbauer spectroscopy, some of which possess good potential as screening methods. Depending on the needs, such as sample size, analysis rate and postulated accuracy, different nuclear techniques may be selected today for nitrogen screening. Some of the techniques discussed have additional potential for carbon or oxygen determination, for measuring depth or lateral N distribution, or for the recognition of the type of chemical N binding. Though most if not all techniques need further development for routine application, they are able to compete with chemical techniques in cost, rate and accuracy. (author)

  10. A scientific model to determine the optimal radiographer staffing component in a nuclear medicine department

    International Nuclear Information System (INIS)

    Shipanga, A.N.; Ellmann, A.

    2004-01-01

    Full text: Introduction: Nuclear medicine in South Africa is developing fast. Much has changed since the constitution of a scientific model for determining an optimum number of radiographer posts in a Nuclear Medicine department in the late 1980's. Aim: The aim of this study was to ascertain whether the number of radiographers required by a Nuclear Medicine department can still be determined according to the norms established in 1988. Methods: A quantitative study using non-experimental evaluation design was conducted to determine the ratios between current radiographer workload and staffing norms. The workload ratios were analysed using the procedures statistics of the Nuclear Medicine department at Tygerberg Hospital. Radiographers provided data about their activities related to patient procedures, including information about the condition of the patients, activities in the radiopharmaceutical laboratory, and patient related administrative tasks. These were factored into an equation relating this data to working hours, including vacation and sick leave. The calculation of Activity Standards and an annual Standard Workload was used to finally calculate the staffing requirements for a Nuclear Medicine department. Results: Preliminary data confirmed that old staffing norms cannot be used in a modern Nuclear Medicine department. Protocols for several types of study have changed, including the additional acquisition of tomographic studies. Interest in the use of time-consuming non-imaging studies has been revived and should be factored Into the equation. Conclusions: All Nuclear Medicine departments In South Africa, where the types of studies performed have changed over the past years, should look carefully at their radiographer staffing ratio to ascertain whether the number of radiographers needed is adequate for the current workload. (author)

  11. Involvement of IGF-1 and MEOX2 in PI3K/Akt1/2 and ERK1/2 pathways mediated proliferation and differentiation of perivascular adipocytes

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Ping, E-mail: lping@sdu.edu.cn [Department of Cardiology, The Second Hospital of Shandong University, No. 247, Beiyuan Road, Shandong, Jinan 250033 (China); Kong, Feng; Wang, Jue [Central Laboratory, The Second Hospital of Shandong University, Shandong, Jinan 250033 (China); Lu, Qinghua [Department of Cardiology, The Second Hospital of Shandong University, No. 247, Beiyuan Road, Shandong, Jinan 250033 (China); Xu, Haijia [Department of Cardiology, Wendeng Central Hospital of Weihai City, Shandong, Weihai 264400 (China); Qi, Tonggang [Central Laboratory, The Second Hospital of Shandong University, Shandong, Jinan 250033 (China); Meng, Juan [Department of Cardiology, The Second Hospital of Shandong University, No. 247, Beiyuan Road, Shandong, Jinan 250033 (China)

    2015-02-01

    Perivascular adipocyte (PVAC) proliferation and differentiation were closely involved in cardiovascular disease. We aimed to investigate whether phosphatidylinositol 3-kinase (PI3K) and mitogen-activated protein kinase (MAPK) signaling pathways enhance PVAC functions activated by insulin-like growth factor 1(IGF-1) and suppressed by mesenchyme homeobox 2 (MEOX2). In this study, PVACs from primary culture were cultured and induced to differentiate. Cell viability assays demonstrated that IGF-1 promoted PVAC proliferation and differentiation. However MEOX2 counteracted these IGF-1-mediated actions. Flow Cytometry revealed that IGF-1 increased S phase cells and decreased apoptosis; however, MEOX2 decreased S phase cells, increased G0–G1 phase cells, and promoted apoptosis. During PVAC proliferation and differentiation, IGF-1 activated PI3K/Akt1/2 and ERK1/2 signaling pathways, upregulated the expression of these signaling proteins and FAS, and increased PVAC lipid content. In contrast, MEOX2 constrained the phosphorylation of ERK1/2 and Akt1/2 protein, down-regulated these signaling molecules and FAS, and decreased PVAC lipid content. Instead, MEOX2 knockdown enhanced the ERK1/2 and Akt1/2 phosphorylation, augmented the expression of these signaling molecules and FAS, and increased PVAC lipid content. Our findings suggested that PI3K/Akt1/2 and ERK1/2 activation mediated by IGF-1 is essential for PVAC proliferation and differentiation, and MEOX2 is a promising therapeutic gene to intervene in the signaling pathways and inhibit PVAC functions. - Highlights: • IGF-1 activated PI3K/Akt2 and ERK1/2 pathways to mediate PVAC proliferation and differentiation. • The expression of ERK1, ERK 2, PI3K, Akt1 and Akt2 showed different change trends between PVAC proliferation and differentiation. • MEOX2 effectively expressed in PVAC, increased early and late cellular apoptosis, and inhibited its proliferation. • MEOX2 depressed PVAC differentiation and FAS expression

  12. Involvement of IGF-1 and MEOX2 in PI3K/Akt1/2 and ERK1/2 pathways mediated proliferation and differentiation of perivascular adipocytes

    International Nuclear Information System (INIS)

    Liu, Ping; Kong, Feng; Wang, Jue; Lu, Qinghua; Xu, Haijia; Qi, Tonggang; Meng, Juan

    2015-01-01

    Perivascular adipocyte (PVAC) proliferation and differentiation were closely involved in cardiovascular disease. We aimed to investigate whether phosphatidylinositol 3-kinase (PI3K) and mitogen-activated protein kinase (MAPK) signaling pathways enhance PVAC functions activated by insulin-like growth factor 1(IGF-1) and suppressed by mesenchyme homeobox 2 (MEOX2). In this study, PVACs from primary culture were cultured and induced to differentiate. Cell viability assays demonstrated that IGF-1 promoted PVAC proliferation and differentiation. However MEOX2 counteracted these IGF-1-mediated actions. Flow Cytometry revealed that IGF-1 increased S phase cells and decreased apoptosis; however, MEOX2 decreased S phase cells, increased G0–G1 phase cells, and promoted apoptosis. During PVAC proliferation and differentiation, IGF-1 activated PI3K/Akt1/2 and ERK1/2 signaling pathways, upregulated the expression of these signaling proteins and FAS, and increased PVAC lipid content. In contrast, MEOX2 constrained the phosphorylation of ERK1/2 and Akt1/2 protein, down-regulated these signaling molecules and FAS, and decreased PVAC lipid content. Instead, MEOX2 knockdown enhanced the ERK1/2 and Akt1/2 phosphorylation, augmented the expression of these signaling molecules and FAS, and increased PVAC lipid content. Our findings suggested that PI3K/Akt1/2 and ERK1/2 activation mediated by IGF-1 is essential for PVAC proliferation and differentiation, and MEOX2 is a promising therapeutic gene to intervene in the signaling pathways and inhibit PVAC functions. - Highlights: • IGF-1 activated PI3K/Akt2 and ERK1/2 pathways to mediate PVAC proliferation and differentiation. • The expression of ERK1, ERK 2, PI3K, Akt1 and Akt2 showed different change trends between PVAC proliferation and differentiation. • MEOX2 effectively expressed in PVAC, increased early and late cellular apoptosis, and inhibited its proliferation. • MEOX2 depressed PVAC differentiation and FAS expression

  13. Development of nuclear methods for determining fluid-dynamic parameters in fluid catalyst cracking reactors

    International Nuclear Information System (INIS)

    Santos, V.A. dos; Dantas, C.C.

    1986-01-01

    Flow parameters of circulating fluidized bed in a simulated Fluid Catalyst Cracking reactor were determined by means of nuclear methods. The parameters were: residence time, density, inventory, circulation rate and radial distribution, for the catalyst; residence time for the gaseous phase. The nuclear methods where the gamma attenuation and the radiotracer. Two tracer techniques were developed, one for tagging of the catalyst by the 59 Fe as intrinsic tracer and another for tagging of the gaseous phase by the CH 3 82 Br as tracer. A detailed description of each measuring technique for all the investigated parameters is included. To carry out the determination for some of parameters a combination of the two methods was also applied. The results and the nuclear data are given in a table. (Author) [pt

  14. Spectrographic determination of lithium in nuclear grade calcium; Determination spectrographique du lithium dans le calcium nucleaire

    Energy Technology Data Exchange (ETDEWEB)

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

    1957-07-01

    A method is described for the spectrographic determination of lithium in calcium. The samples are converted directly to CaCO{sub 3}. A method of fractional distillation in the arc, using KCl as carrier, makes it possible to detect and measure the Li content to 0,1 ppm. (author) [French] On decrit une methode de determination spectrographique de Li dans Ca. Les echantillons sont transformes d'une facon simple en CO{sub 3}Ca. Une methode de distillation fractionnee dans l'arc utilisant KCl comme entraineur permet la detection et le dosage de teneurs de Li jusqu'a 0,1 ppm. (auteur)

  15. Determination of burn-up of irradiated nuclear fuels using mass spectrometry

    International Nuclear Information System (INIS)

    Jagadish Kumar, S.; Telmore, V.M.; Shah, R.V.; Sasi Bhushan, K.; Paul, Sumana; Kumar, Pranaw; Rao, Radhika M.; Jaison, P.G.

    2017-01-01

    Burn-up defined as the atom percent fission, is a vital parameter used for assessing the performance of nuclear fuel during its irradiation in the reactor. Accurate data on the actinide isotopes are also essential for the reliable accountability of nuclear materials and for nuclear safeguards. Both destructive and non-destructive methods are employed in the post-irradiation analysis for the burn-up measurements. Though non-destructive methods are preferred from the point view of remote handling of irradiated fuels with high radioactivity, they do not provide the high accuracy as achieved by the chemical analysis methods. Thus destructive radiochemical and chemical analyses are still the established reference methods for accurate and reliable burn-up determination of irradiated nuclear fuels. In the destructive method, burn-up of irradiated nuclear fuel is determined by correlating the amount of a fission product formed during irradiation with that of heavy elements. Thus the destructive experimental determination of burn-up involves the dissolution of irradiated fuel samples followed by the separation and determination of heavy elements and fission product(s) to be used as burn-up monitor(s). Another approach for the experimental determination of burn-up is based on the changes in the abundances of the heavy element isotopes. A widely accepted method for burn-up determination is based on stable "1"4"8Nd and "1"3"9La as burn-up monitors. Several properties such as non-volatility, nearly same yields for thermal fissions of "2"3"5U and "2"3"9Pu etc justifies the selection of "1"4"8Nd as a burn-up monitor

  16. Development and implementation of methods for determination of the origin of nuclear materials

    International Nuclear Information System (INIS)

    Wallenius, M.; Pajo, L.; Mayer, K.

    2001-01-01

    The determination of the origin of seized nuclear material is important for authorities in the context of the criminal investigation, in order to return the material to its last legal owner and to help preventing any further diversion of material from this source. Origin determination is based on a complex pattern of parameters obtained through analytical measurements. The information required to determine the origin of nuclear materials may be divided into two categories: endogenous information (e.g. age or mode of production of the material) which is self-explanatory; whereas exogenous information (e.g. dimensions, surface roughness, impurities) requires a database to which the parameters can be compared. The Institute for Transuranium Elements has developed methods to determine characteristic parameters like impurities, surface roughness, or microstructural information. Furthermore, a database was set up containing relevant information on reactor fuels. (author)

  17. Acceptance criteria for determining armed response force size at nuclear power plants

    International Nuclear Information System (INIS)

    1983-02-01

    This guidance document contains acceptance criteria to be used in the NRC license review process. It consists of a scored worksheet and guidelines for interpreting the worksheet score that can be used in determining the adequacy of the armed response force size at a nuclear power reactor facility

  18. The determination of the in situ structure by nuclear spin contrast variation

    Energy Technology Data Exchange (ETDEWEB)

    Stuhrmann, H.B. [GKSS Forschungszentrum, Geesthacht (Germany); Nierhaus, K.H. [Max-Planch-Institut fuer Molekulare Genetik, Berlin (Germany)

    1994-12-31

    Polarized neutron scattering from polarized nuclear spins in hydrogenous substances opens a new way of contrast variation. The enhanced contrast due to proton spin polarization was used for the in situ structure determination of tRNA of the functional complex of the E.coli ribosome.

  19. Quantitative determination of impurities in nuclear grade aluminum by Flame-Atomic Absorption Spectrometry

    International Nuclear Information System (INIS)

    Jat, J.R.; Nayak, A.K.; Balaji Rao, Y.; Ravindra, H.R.

    2013-01-01

    The paper deals with quantitative determination of impurity elements in nuclear grade aluminum, used as fin tubes in research reactors, by Flame-Atomic Absorption Spectrometry (F-AAS). The results have been compared with those obtained by Inductively Coupled Plasma Atomic Emission Spectrometry (ICP-AES) method. Experimental conditions used in both the methods are given in the paper. (author)

  20. Determination of activation level energy of nuclear isomers by calibration of microspectra of radioactive sources

    International Nuclear Information System (INIS)

    Veres, A.; Pavlicsek, I.

    1980-01-01

    Nuclear isomers with unknown activation level were irradiated by calibrated radioactive sources. The integral cross sections were calculated for different energies of the sources. The activation energy was given by values coinciding with each other within the limits of error. The method made the determination of the unknown level of 1180+-10 keV of 195 Pt nucleus possible. (author)

  1. The maximum entropy determination of nuclear densities of calcium isotopes from elastic scattering of alpha particles

    International Nuclear Information System (INIS)

    Engel, Y.M.; Friedman, E.; Levine, R.D.

    1982-01-01

    Radial moments of the real part of the optical potential for elastic scattering of 104 MeV α particles are used as constraints, in determining the nuclear density of maximal entropy. The potential is related to the density by the folding model. (orig.)

  2. Reserve seismic capacity determination of a nuclear power plant braced frame with piping

    International Nuclear Information System (INIS)

    Nelson, T.A.

    1979-01-01

    The Lawrence Livermore Laboratory has been asked by the U.S. Nuclear Regulatory Commission to investigate the inelastic behavior of a representative non-category I structure to determine the amount of reserve seismic capacity that is available beyond elastic design levels. This reserve capacity can be an important consideration when evaluating the ability of existing structures to withstand upgraded seismic hazards. (orig.)

  3. Assessment procedure and probability determination methods of aircraft crash events in siting for nuclear power plants

    International Nuclear Information System (INIS)

    Zheng Qiyan; Zhang Lijun; Huang Weiqi; Yin Qingliao

    2010-01-01

    Assessment procedure of aircraft crash events in siting for nuclear power plants, and the methods of probability determination in two different stages of prelimi- nary screening and detailed evaluation are introduced in this paper. Except for general air traffic, airport operations and aircraft in the corridor, the probability of aircraft crash by military operation in the military airspaces is considered here. (authors)

  4. Determination of metallic impurities in nuclearly pure uranium compounds by electrothermal spectrophotometry

    International Nuclear Information System (INIS)

    Franco, M.B.

    1986-01-01

    Atomic absorption spectrometry, with electrothermal atomization, has been used for the determination of Al, Cd, Cr, Fe, Mn and Ni in uranium oxide standards. The analysis were performed without sample dissolution and without uranium chemical separation. This technique is adequate for the qualification of nuclearly pure uranium, according to the standard specifications. (Author) [pt

  5. The determination of the in situ structure by nuclear spin contrast variation

    International Nuclear Information System (INIS)

    Stuhrmann, H.B.; Nierhaus, K.H.

    1994-01-01

    Polarized neutron scattering from polarized nuclear spins in hydrogenous substances opens a new way of contrast variation. The enhanced contrast due to proton spin polarization was used for the in situ structure determination of tRNA of the functional complex of the E.coli ribosome

  6. Report to the Nuclear Regulatory Commission from the staff panel on the Commission's determination of an Extraordinary Nuclear Occurrence (ENO)

    International Nuclear Information System (INIS)

    1980-01-01

    The Panel finds that the first criterion, pertaining to whether the accident caused a discharge of radioactive material or levels of radiation offsite as defined in 10 CFR 140.84, has not been met. It further finds that there is presently insufficient information to support any definitive finding as to whether or not the second criterion, relating to damage to persons or property offsite as defined in 10 CFR 140.85, has been met. Since the Panel has not found that both criteria have been met, it recommends that the Commission determine that the accident at Three Mile Island did not constitute an extraordinary nuclear occurrence

  7. Report to the Nuclear Regulatory Commission from the staff panel on the Commission's determination of an Extraordinary Nuclear Occurrence (ENO)

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    The Panel finds that the first criterion, pertaining to whether the accident caused a discharge of radioactive material or levels of radiation offsite as defined in 10 CFR 140.84, has not been met. It further finds that there is presently insufficient information to support any definitive finding as to whether or not the second criterion, relating to damage to persons or property offsite as defined in 10 CFR 140.85, has been met. Since the Panel has not found that both criteria have been met, it recommends that the Commission determine that the accident at Three Mile Island did not constitute an extraordinary nuclear occurrence.

  8. The use of voltammetry for determining uranium and associated elements in compounds of nuclear interest

    International Nuclear Information System (INIS)

    Carvalho, F.M.S. de.

    1988-01-01

    The determination of uranium and some trace elements found as impurities in nuclear materials by the voltammetric technique using the hanging mercury drop electrode is presented. Emphasis is given to the determination of uranium, of major interest. Europium and ytterbium are simultaneously determined in fractions of individual lanthanides. A procedure for the simultaneous determination of copper, cadmium, nickel and zinc in water, industrial effluents and uranium compounds is discussed. The advantage of the procedure is its simplicity and easiness of execution, with excellent precision and accuracy. (author) [pt

  9. A simple technique to determine the size distribution of nuclear crater fallback and ejecta

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, II, Brooks D [U.S. Army Engineer Nuclear Cratering Group, Lawrence Radiation Laboratory, Livermore, CA (United States)

    1970-05-15

    This report describes the results of an investigation to find an economic method for determining the block size distribution of nuclear crater fallback and ejecta. It is shown that the modal analysis method of determining relative proportions can be applied with the use of a special sampling technique, to provide a size distribution curve for clastic materials similar to one obtainable by sieving and weighing the same materials.

  10. A simple technique to determine the size distribution of nuclear crater fallback and ejecta

    International Nuclear Information System (INIS)

    Anderson, Brooks D. II

    1970-01-01

    This report describes the results of an investigation to find an economic method for determining the block size distribution of nuclear crater fallback and ejecta. It is shown that the modal analysis method of determining relative proportions can be applied with the use of a special sampling technique, to provide a size distribution curve for clastic materials similar to one obtainable by sieving and weighing the same materials

  11. Volumetric determination of hydroxide, aluminate, and carbonate in alkaline solutions of nuclear waste

    International Nuclear Information System (INIS)

    Baumann, E.W.

    1975-06-01

    An integrated procedure was developed for determining OH - , Al(OH) 4 - , and CO 3 2- in alkaline nuclear waste. The free alkali, the hydroxide released when Al(OH) 3 is complexed with oxalate, and the precipitated BaCO 3 were determined by acidimetric titration. With a 50-μl sample, the relative standard deviations were 1 to 2 percent for nonradioactive test solutions and 2 to 5 percent for radioactive process solutions. (U.S.)

  12. Determining the potential volume of industrial process steam to be generated in nuclear facilities

    International Nuclear Information System (INIS)

    Jobsky, T.

    1990-01-01

    The present study serves to determine the market potential of nuclear energy for industrial process steam supply according to branches and sites in the Federal Republic of Germany (excluding the new East German Laender). On the nuclear plant side two HTR reference plants with different unit powers of 200 MWth (HTR-Modul) and 100 MWth are investigated. An essential result in analysing the nuclear market potential is the finding that the number of potential users and sites will triple if smaller unit sizes were introduced. This corresponds to an increase in nuclear plant potential from 28 units of 200 MWth each to 91 units of 100 MWth on the assumptions made in this study. A comparison of economic efficiency between fossil-fired power production plants and the HTR-Modul shows the competitiveness of nuclear process steam and electricity production in the base load range. A single-site evaluation for the centres of energy demand competes conceptually with a combined heat supply by nuclear long-distance energy. This integrated supply concept makes it possible to supply considerably more industrial companies with process steam while reducing the number of sites, since the heat requirements of smaller sites can also be covered by the integrated system. (orig.) [de

  13. Cinnamaldehyde and eugenol change the expression folds of AKT1 and DKC1 genes and decrease the telomere length of human adipose-derived stem cells (hASCs: An experimental and in silico study

    Directory of Open Access Journals (Sweden)

    Abdorrahim Absalan

    2017-03-01

    Full Text Available Objective(s: To investigate the effect of cinnamaldehyde and eugenol on the telomere-dependent senescence of stem cells. In addition, to search the probable targets of mentioned phytochemicals between human telomere interacting proteins (TIPs using in silico studies. Materials and Methods: Human adipose derived stem cells (hASCs were studied under treatments with 2.5 µM/ml cinnamaldehyde, 0.1 µg/ml eugenol, 0.01% DMSO or any additive. The expression of TERT, AKT1 and DKC1 genes and the telomere length were assessed over 48-hr treatment. In addition, docking study was conducted to show probable ways through which phytochemicals interact with TIPs. Results: Treated and untreated hASCs had undetectable TERT expression, but they did affect the AKT1 and DKC1 expression levels (CI=0.95; P

  14. A method for determining the content of knowledge training for nuclear professionals

    International Nuclear Information System (INIS)

    Scott, C.K.

    2004-01-01

    A developer of knowledge training materials for nuclear professionals is faced with the challenge of determining the appropriate scope and depth of training. This paper presents a method for establishing the content starting from overall objectives of the activity and breaking it down into the job and task level of an individual's specific jobs and tasks. Nuclear safety training is used as an example. In this case there are four stages of break down in the knowledge base before its implementation in jobs and tasks of the station's work processes. This process also satisfies the training principles for enabling effective operational decision making. (author)

  15. The discussion of a method to determine the underground destruction range of nuclear earth penetrator bursts

    International Nuclear Information System (INIS)

    Geng Xiaobing; Zhang Zhongshan

    2007-01-01

    This thesis chooses cross hole seismic tomography to determine the destruction range of surrounded rock in virtue of the characteristic of nuclear earth penetrator explosion.According to Fermat's principle, ray tracing method-the shortest path method suggested by Moser used, a programme was produced to calculate seismic travel time and then to simulate the collection the practical travel time data. The Genetic Algorithm is adopted as the inversion method to simulate in accordance with the crater model of nuclear earth penetrator explosion. (authors)

  16. Compartment modelling in nuclear medicine: a new program for the determination of transfer coefficients

    International Nuclear Information System (INIS)

    Hallstadius, L.

    1986-01-01

    In many investigations concerning transport/exchange of matter in a natural system, e.g. functional studies in nuclear medicine, it is advantageous to relate experimental results to a model of the system. A new computer program is presented for the determination of linear transfer coefficients in a compartment model from experimentally observed time-compartment content curves. The program performs a least-square fit with the specified precision of the observed values as weight factors. The resulting uncertainty in the calculated transfer coefficients may also be assessed. The application of the program in nuclear medicine is demonstrated and discussed. (author)

  17. AKT1 as the PageRank hub gene is associated with melanoma and its functional annotation is highly related to the estrogen signaling pathway that may regulate the growth of melanoma.

    Science.gov (United States)

    Zhao, Jingjing; Zeng, Xue; Song, Ping; Wu, Xiaohong; Shi, Hongbo

    2016-10-01

    In order to detect the disease-associated genes and their gene interaction function and association with melanoma mechanisms, we identified a total of 1,310 differentially expressed genes (DEGs) from the Gene Expression Omnibus database GSE3189 with FDR 2 using the R package. After constructing the gene interaction network by STRING with the selected DEGs, we applied a statistical approach to identify the topological hub genes with PageRank score. Forty-four genes were identified in this network and AKT1 was selected as the most important hub gene. The AKT1 gene encodes a serine‑threonine protein kinase (AKT). High expression of AKT is involved in the resistance of cell apoptosis as well as adaptive resistance to treatment in melanoma. Our results indicated that AKT1 with a higher expression in melanoma showed enriched binding sites in the negative regulation of response to external stimulus, which enables cells to adapt to changes in external stimulation for survival. Another finding was that AKT regulated the lipid metabolic process and may be involved in melanoma progression and promotion of tumor growth through gene enrichment function analysis. Two highlighted pathways were detected in our study: i) the estrogen signaling pathway modulates the immune tolerance and resistance to cell apoptosis, which contributes to the growth of melanoma and ii) the RAP1 signaling pathway which regulates focal adhesion (FA) negative feedback to cell migration and invasion in melanoma. Our studies highlighted the top differentially expressed gene AKT1 and its correlation with the estrogen signaling and RAP1 signaling pathways to alter the proliferation and apoptosis of melanoma cells. Analysis of the enrichment functions of genes associated with melanoma will help us find the exact mechanism of melanoma and advance the full potential of newly targeted cancer therapy.

  18. Involvement of IGF-1 and MEOX2 in PI3K/Akt1/2 and ERK1/2 pathways mediated proliferation and differentiation of perivascular adipocytes.

    Science.gov (United States)

    Liu, Ping; Kong, Feng; Wang, Jue; Lu, Qinghua; Xu, Haijia; Qi, Tonggang; Meng, Juan

    2015-02-01

    Perivascular adipocyte (PVAC) proliferation and differentiation were closely involved in cardiovascular disease. We aimed to investigate whether phosphatidylinositol 3-kinase (PI3K) and mitogen-activated protein kinase (MAPK) signaling pathways enhance PVAC functions activated by insulin-like growth factor 1(IGF-1) and suppressed by mesenchyme homeobox 2 (MEOX2). In this study, PVACs from primary culture were cultured and induced to differentiate. Cell viability assays demonstrated that IGF-1 promoted PVAC proliferation and differentiation. However MEOX2 counteracted these IGF-1-mediated actions. Flow Cytometry revealed that IGF-1 increased S phase cells and decreased apoptosis; however, MEOX2 decreased S phase cells, increased G0-G1 phase cells, and promoted apoptosis. During PVAC proliferation and differentiation, IGF-1 activated PI3K/Akt1/2 and ERK1/2 signaling pathways, upregulated the expression of these signaling proteins and FAS, and increased PVAC lipid content. In contrast, MEOX2 constrained the phosphorylation of ERK1/2 and Akt1/2 protein, down-regulated these signaling molecules and FAS, and decreased PVAC lipid content. Instead, MEOX2 knockdown enhanced the ERK1/2 and Akt1/2 phosphorylation, augmented the expression of these signaling molecules and FAS, and increased PVAC lipid content. Our findings suggested that PI3K/Akt1/2 and ERK1/2 activation mediated by IGF-1 is essential for PVAC proliferation and differentiation, and MEOX2 is a promising therapeutic gene to intervene in the signaling pathways and inhibit PVAC functions. Copyright © 2014 Elsevier Inc. All rights reserved.

  19. Development of anodic stripping voltametry for the determination of palladium in high level nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Bhardwaj, T. K. [North Carolina State University, Raleigh (United States); Sharma, H. S.; Affarwal, S. K. [Bhabha Atomic Research Centre, Mumbai (India); Jain, P. C. [Meerut College, Meerut (India)

    2012-12-15

    Deposition potential, deposition time, square wave frequency, rotation speed of the rotating disc electrode, and palladium concentration were studied on a Glassy Carbon Electrode (GCE) in 0.01M HCl for the determination of palladium in High Level Nuclear Waste (HLNW) by anodic stripping voltammetry. Experimental conditions were optimized for the determination of palladium at two different, 10-8 and 10-7 M, levels. Error and standard deviation of this method were under 1% for all palladium standard solutions. The developed technique was successfully applied as a subsidiary method for the determination of palladium in simulated high level nuclear waste with very good precision and high accuracy (under 1 % error and standard deviation).

  20. Determination of internationally controlled materials according to provisions of the law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1984-01-01

    The internationally controlled materials determined according to the law for nuclear source materials, etc. are the following: nuclear source materials, nuclear fuel materials, moderating materials, facilities including reactors, etc. sold, transferred, etc. to Japan according to the agreements for peaceful uses of atomic energy between Japan, and the United States, the United Kingdom, Canada, Australia and France by the respective governments and those organs under them; nuclear fuel materials resulting from usage of the above sold and transferred materials, facilities; nuclear fuel materials sold to Japan according to agreements set by the International Atomic Energy Agency; nuclear fuel materials involved with the safeguards in nuclear weapons non-proliferation treaty with IAEA. (Mori, K.)

  1. Application of a methodology to determine priorities for nuclear power plant safety issues

    International Nuclear Information System (INIS)

    Daling, P.M.

    1988-01-01

    The Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) is sponsoring a research program to determine priorities of nuclear power plant safety issues. A methodology has been developed at the Pacific Northwest Laboratory (PNL) to provide technical assistance in the development of risk and cost estimates for implementing resolutions to the safety issues. The information development methods are intended to provide the NRC with a consistent level of information for use in ranking the issues. The NRC uses this information, along with judgmental factors, to rank the issues for further consideration by the NRC staff. The primary purpose of the priority rankings are to assist in the allocation of resources to issues that have high potential for reducing public risk as well as to remove issues from further consideration that have little safety significance

  2. An investigation on technical bases of emergency plan zone determination of Qinshan Nuclear Power Base

    International Nuclear Information System (INIS)

    Duan Xuyi

    2000-01-01

    According to the general principal and the basic method of determination of emergency zone and safety criteria and in the light of the environmental and accidental release characteristic of Qinshan Nuclear Power Base, the expectation dose of assumed accident of each plant was compared and analyzed. In consideration of the impact factor of the size of emergency plan zone and referring to the information of emergency plan zone determination of other country in the world, the suggestions of determination method of emergency plan zone are proposed

  3. Use of nuclear methods for the analysis of materials and the determination of concentration profiles

    International Nuclear Information System (INIS)

    Darras, R.

    1976-01-01

    The possibilities of the activation analysis and nuclear reaction analysis are presented. These methods allow the oligo-elements and impurities (in trace amounts) to be determined in materials with accuracy and a high sensitivity. They can also be applied to the determination of major elements in a small amount of materials. Surface analysis and concentration profile determination are possible when the nature and energy of the incident particles are judiciously selected. Exemples of analysis of steels, pure iron and refractories are given [fr

  4. Determination of karst collapse intensity indicator in area of nuclear power plant construction using incomplete data

    International Nuclear Information System (INIS)

    Sharapov, R

    2014-01-01

    The paper deals with the definition of karst collapse intensity. The technique for determining the intensity of karst formation and collapse on the basis of calculation and probabilistic method is given. Karst collapse formation is affected by a great variety of natural and anthropogenic factors. Each factor can vary quite widely. The paper describes a technique for determining karst collapse intensity from incomplete data. It uses karst processes monitoring data in the area and monitoring data of areas with similar values of the most significant factors leading to the karst collapses. The method used for determination of karst collapse intensity indicator in area of Nizhny Novgorod nuclear power plant construction

  5. Determination of zirconium 93 and molybdenum 93 in reprocessing nuclear waste

    International Nuclear Information System (INIS)

    Puech, P.

    1998-01-01

    The aim of this work is to find new determination methods of zirconium 93 and molybdenum 93 (two long-lived radioelements) contained in reprocessing nuclear waste. 93 Zr has a very long period: 1.5 * 10 6 years. The measurement of this isotope is more performing by the ICP-MS method than by the classical radiochemical measurement methods. 93 Mo disintegrates with a radioactive period of 4000 years and can be detected by radiochemical measurement in particular by X spectrometry. But these radioelements cannot be directly measured on the reprocessing nuclear waste; they require a preliminary chemical separation (removing the radioelements able to interfere and those responsible of the radioactivity of the nuclear waste). The separation is implemented with very potentially selective techniques, using Mo and Zr specific extracting molecules: solvent extraction, emulsified liquid membrane extraction and liquid chromatography extraction (on a resin impregnated by solvent). Studies carried out in CEA/Cadarache, on a synthetic solution simulating a reprocessing nuclear waste, have allowed to show the selective properties of the L'-benzoinoxime for extracting Mo and of TBP for extracting Zr for the three studied techniques. The optimal extraction and separation conditions have been reached with a methodology including experiment plans. At last, the methods have been tested on real reprocessing nuclear waste at Cogema/La Hague. 93 Zr and 93 Mo have been measured in a dissolution solution and in a fission product solution. The obtained values are 2 * 10 6 Bq/l and 10 7 Bq/l for 93 Zr and 500 Bq/l for 93 Mo in a dissolution solution. These methods have allowed to determine too the isotopic compositions for Mo and Zr elements contained in reprocessing nuclear waste. The results are in accordance with those obtained with the Cesar code. (O.M.)

  6. Determining the nuclear data uncertainty on MONK10 and WIMS10 criticality calculations

    Directory of Open Access Journals (Sweden)

    Ware Tim

    2017-01-01

    Full Text Available The ANSWERS Software Service is developing a number of techniques to better understand and quantify uncertainty on calculations of the neutron multiplication factor, k-effective, in nuclear fuel and other systems containing fissile material. The uncertainty on the calculated k-effective arises from a number of sources, including nuclear data uncertainties, manufacturing tolerances, modelling approximations and, for Monte Carlo simulation, stochastic uncertainty. For determining the uncertainties due to nuclear data, a set of application libraries have been generated for use with the MONK10 Monte Carlo and the WIMS10 deterministic criticality and reactor physics codes. This paper overviews the generation of these nuclear data libraries by Latin hypercube sampling of JEFF-3.1.2 evaluated data based upon a library of covariance data taken from JEFF, ENDF/B, JENDL and TENDL evaluations. Criticality calculations have been performed with MONK10 and WIMS10 using these sampled libraries for a number of benchmark models of fissile systems. Results are presented which show the uncertainty on k-effective for these systems arising from the uncertainty on the input nuclear data.

  7. Determination of discharge authorizations for French basic nuclear installations 58 and public information

    International Nuclear Information System (INIS)

    Tabard, Laurence; Conte, Dorothee

    2013-01-01

    The determination of discharge authorized limits for a French nuclear site is initiated by the request of the operator, based on the maximum nuclear and chemical inventory that could be released during normal operating conditions, accompanied with justifications. Request and justifications are analyzed and discussed by the ASN and the IRSN, taking into account nuclear and chemical inventories expected inside BNI, current regulations (BNI specific regulation, environment code, public health code), operating feedback (release feedback for an operating BNI, feedback coming from other nuclear sites or installations, etc.) and best available technologies that can be used to treat liquid or gaseous waste before release. After taking into account potential suggestions coming from public information or public enquiry concerning the operator request, the discharge authorized limits are settled down in specific ASN prescriptions that have to be ratified by the State secretaries in charge of nuclear safety. The whole process runs through 2 or 3 years to be achieved. Communication has revealed to be quite an uneasy task, even for administrative procedures. This aspect is mostly tested while communicating about events. Consequences of this communication can hardly be foreseen because of multiple external parameters like: news on the front pages at the same moment; historic communication difficulties still in the public mind; technical vocabulary not easily understood; public fear of things being hidden; power of ecologist or non-governmental associations. (authors)

  8. Determining the nuclear data uncertainty on MONK10 and WIMS10 criticality calculations

    Science.gov (United States)

    Ware, Tim; Dobson, Geoff; Hanlon, David; Hiles, Richard; Mason, Robert; Perry, Ray

    2017-09-01

    The ANSWERS Software Service is developing a number of techniques to better understand and quantify uncertainty on calculations of the neutron multiplication factor, k-effective, in nuclear fuel and other systems containing fissile material. The uncertainty on the calculated k-effective arises from a number of sources, including nuclear data uncertainties, manufacturing tolerances, modelling approximations and, for Monte Carlo simulation, stochastic uncertainty. For determining the uncertainties due to nuclear data, a set of application libraries have been generated for use with the MONK10 Monte Carlo and the WIMS10 deterministic criticality and reactor physics codes. This paper overviews the generation of these nuclear data libraries by Latin hypercube sampling of JEFF-3.1.2 evaluated data based upon a library of covariance data taken from JEFF, ENDF/B, JENDL and TENDL evaluations. Criticality calculations have been performed with MONK10 and WIMS10 using these sampled libraries for a number of benchmark models of fissile systems. Results are presented which show the uncertainty on k-effective for these systems arising from the uncertainty on the input nuclear data.

  9. Determination of Nuclear Track Parameters for LR-115 Detector by Using of MATLAB Software Technique

    International Nuclear Information System (INIS)

    AL-Jomaily, F.M.; AL-joburi, H.A.; Mheemeed, A.K.

    2013-01-01

    The nuclear track detector parameters, such as nuclear track diameter D(μm), number of track N T and area of track A T were determined by using MATLAB software technique for IR-115 detector irradiated by alpha particle from 241 Am source under 1.5, 2.5 and 3.5 MeV at etching time T B of 90, 120, 150 and 180 min.By using the image analysis of MATLAB software for nuclear track, the full width at half maximum FWHM and relative resolution R% were calculated for each energy of alpha particles.In this study, it was shown that increasing the alpha energy on the IR-115 detector leads to increased etching time T B and the dropping of R% to minimum value, and then reach a stable value before dropping at values 1.5, 2.5 MeV and unstable at 3.5 MeV. Imaging analysis by MATLAB technique which used in this study reflect good and accurate results for nuclear track detector parameters and we recommend using this technique for determination of these parameters

  10. Particle induced X-ray emission and complementary nuclear methods for trace element determination; Plenary lecture

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, S A.E. [Lund Univ. (Sweden). Dept. of Nuclear Physics

    1992-03-01

    In this review the state-of-the-art of particle induced X-ray emission (PIXE) methods for the determination of trace elements is described. The developmental work has mostly been carried out in nuclear physics laboratories, where accelerators are available, but now the increased interest has led to the establishment of other dedicated PIXE facilities. The reason for this interest is the versatility, high sensitivity and multi-element capability of PIXE analysis. A further very important advantage is that PIXE can be combined with the microbeam technique, which makes elemental mapping with a spatial resolution of about 1 {mu}m possible. As a technique, PIXE can also be combined with other nuclear reactions such as elastic scattering and particle-induced gamma emission, so that light elements can be determined. The usefulness of PIXE is illustrated by a number of typical applications in biology, medicine, geology, air pollution research, archaeology and the arts. (author).

  11. Spectrographic determination of metallic impurities in organic coolants for nuclear reactors

    International Nuclear Information System (INIS)

    Martin Munoz, M.; Alvarez Gonzalez, F.

    1969-01-01

    A spectrochemical method for determining metallic impurities in organic coolants for nuclear reactors is given. The organic matter in solid samples is eliminated by controlled distillation and dry ashing in the presence of magnesium oxide as carrier. Liquid, samples are vacuum distillated. The residue is analyzed by carrier distillation and by total burning techniques. The analytical results are discussed and compared with those obtained destroying the organic matter without carrier and using the copper spark technique. (Author) 12 refs

  12. Intercomparison run for uranium and tritium determination in urine samples, organised by Nuclear Regulatory Authority, Argentina

    CERN Document Server

    Serdeiro, N H; Equillor, H E

    2003-01-01

    The Nuclear Regulatory Authority (ARN), Argentina, has carried out an intercomparison run for tritium and uranium determination in urine, in November 2002. The aim of this exercise was to assess the performance of the laboratories that usually inform these radionuclides and to provide technical support in order to have an appropriate occupational monitoring in vitro. In the present work, the results of the intercomparison and the assessment of each laboratory are published.

  13. Tests for determining impact resistance and strength of glass used for nuclear waste disposal

    International Nuclear Information System (INIS)

    Bunnell, L.R.

    1979-05-01

    Tests are described for determining the impact resistance (Section A) and static tensile strength (Section B) of glasses containing simulated or actual nuclear wastes. This report describes the development and use of these tests to rank different glasses, to assess effects of devitrification, and to examine the effect of impact energy on resulting surface area. For clarity this report is divided into two sections, Impact Resistance and Tensile Strength

  14. Intercomparison run for uranium and tritium determination in urine samples, organised by Nuclear Regulatory Authority, Argentina

    International Nuclear Information System (INIS)

    Serdeiro, Nelida H.; Equillor, Hugo E.; Bonino, Nestor O.

    2003-01-01

    The Nuclear Regulatory Authority (ARN), Argentina, has carried out an intercomparison run for tritium and uranium determination in urine, in November 2002. The aim of this exercise was to assess the performance of the laboratories that usually inform these radionuclides and to provide technical support in order to have an appropriate occupational monitoring in vitro. In the present work, the results of the intercomparison and the assessment of each laboratory are published. (author)

  15. Determination of plutonium in nuclear fuel materials by controlled potential coulometry

    International Nuclear Information System (INIS)

    Ambolikar, A.S.; Pillai, Jisha S.; Sharma, M.K.; Kamat, J.V.; Aggarwal, S.K.

    2011-01-01

    Accurate knowledge of Pu content in nuclear fuel materials is an important requirement for the purpose of chemical quality control, nuclear material accounting and process control. Biamperometry and potentiometry techniques are widely employed for the determination of Pu. These redox electroanalytical based methods are capable of meeting the requirements of high accuracy and precision using milligram amounts of the analyte. However, use of chemical reagents to carry out redox reactions in these methodologies generates radioactive liquid waste which needs to be processed to recover plutonium. In coulometric technique, change in the oxidation state of an electro active species is carried out by charge transfer on an electrode surface, hence chemical reagents as well as chemical standards required for the redox titration based methods are eliminated and analytical waste generated is free from metallic impurities. Therefore the determination of Pu in nuclear fuel materials by coulometry is an attractive option. In view of this, controlled potential coulometric methods have been developed in our laboratory for variety of applications at different stages of nuclear fuel cycle. In the early stage of coulometry developments in our laboratory, coulometers procured from EG and G Princeton Applied Research Corporation were employed. After prolong use, these instruments were showing ageing and hence indigenously built controlled potential coulometer was procured. Performance evaluation studies of these coulometers were reported from our laboratory for the determination of uranium and plutonium in working chemical assay standards. In this paper, we present studies carried out on the determination of plutonium in Pu-alloy and (U, Pu) C samples employing the same indigenous coulometer

  16. Determination of nuclear cross-section of 81Br (n,,,) Br82 reaction by ...

    African Journals Online (AJOL)

    ... flux of 4.2 x 1013 n cm-2 s-1. The BaBr2 was chemically processed and measured as Hydrogen Bromide (HBr82). The value of nuclear cross-section was determined to be 2.1 0.2 barns, which falls within the range of values as previously reported elsewhere. (Journal of Applied Science and Technology: 2001 6(1-2): 4-6) ...

  17. Determination of water in nuclear materials by means of the Karl Fischer method

    International Nuclear Information System (INIS)

    Pereira, W.; Rocha, S.M.R.; Atalla, L.T.; Abrao, A.

    1987-06-01

    Karl Fischer Method was adapted for water determination in uranium coumpounds and substances of nuclear interest, by using a comercial equipment. The experimental conditions for the analysis of U 3 O 8 , UO 3 , UO 2 , UF 4 KFnHF and (NH 4 ) 4 UO 2 (CO 3 ) 3 were established. The influence of the agitation and contact time between sample and solvent, of the sample weight, of the reaction end point determination and of the sample granulometry on the precision and accuracy of results was also studied. (Author) [pt

  18. Nuclear charge radii of 8,9Li determined by laser spectroscopy

    International Nuclear Information System (INIS)

    Ewald, G.; Dax, A.; Goette, S.; Kirchner, R.; Kluge, H.J.; Kuehl, T.; Sanchez, R.; Wojtaszek, A.; Noertershaeuser, W.; Drake, G.W.F.; Yan, Z.C.; Zimmermann, C.

    2004-06-01

    The 2S → 3S transition of 6,7,8,9 Li was studied by high-resolution laser spectroscopy using two-photon Doppler-free excitation and resonance-ionization detection. The hyperfine structure splitting and the isotope shift were determined with precision at the 100 kHz level. Combined with recent theoretical work, the changes in nuclear charge radii of 8,9 Li were determined. These are now the lightest short-lived isotopes for which the charge radii have been measured. It is found that the charge radii monotonically decrease with increasing neutron number from 6 Li to 9 Li. (orig.)

  19. Determination of uranium in uranyl nitrate solutions of nuclear grade quality - Gravimetric method

    International Nuclear Information System (INIS)

    1990-01-01

    This international Standard specifies a precise and accurate gravimetric method for determining the uranium content in uranyl nitrate product solutions of nuclear grade quality at concentrations above 100 g/l of uranium. Non-volatile impurities influence the accuracy of the method. Uranyl nitrate is converted into uranium octoxide (U 3 O 8 ) by ignition in air to constant mass at 900 deg. C ± 10 deg. C. Calculation of the uranium content in the sample using a gravimetric conversion factor which depends on the isotopic composition of the uranium. The isotopic composition is determined by mass spectrometry

  20. In-flow technology for the determination of Sr-90 concentrations in nuclear power plants

    International Nuclear Information System (INIS)

    Dissing, E.

    1982-01-01

    Outlines for a future work concerning in-flow surveillance of Sr-90 in nuclear plant process treams have been studied. The many problems involved with the task of on-line Sr-90 determination were approached in two different ways, one applying β-counting of the 64-hour daughter Y-60 with the use of the process stream itself as a Cerenkov scintillator and the other - indirect - using simultaneous measurement of the concentrations of Sr-91 and Sr-92 for the determination of the leakage route for strontium. (Author)

  1. Isolation and activity determination of 99Tc in nuclear waste by liquid scintillation counting

    International Nuclear Information System (INIS)

    Reis Junior, Aluisio S.; Temba, Eliane S.C.; Kastner, Geraldo F.; Monteiro, Roberto P.G.

    2011-01-01

    A radiochemical separation and purification for technetium was proposed for radioactive waste in which rhenium is to be used as a yield monitor. The separation was performed by anion exchange chromatography and the purification was performed by extraction chromatography using a TEVA resin.The determination of 99 Tc was by liquid scintillation counting and rhenium was activated by Triga Mark 1 research reactor and measured by gamma spectrometry. Some real samples of nuclear waste such as evaporator concentrate and filter were analysed. The chemical recovery determined using rhenium as tracer was around 90 %. (author)

  2. Determination of 93Zr in medium and low level radioactive wastes from Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    Oliveira, Thiago C.; Oliveira, Arno H.

    2015-01-01

    The majority of long-lived radionuclides produced in the nuclear power plants can be regarded as difficult-to-measure radionuclides (RDM), hence chemical separation is necessary before the nuclear measurement of them. The zirconium isotope 93 Zr is a long-lived pure β-particle-emitting radionuclide produced from 235 U fission and from neutron activation of the stable isotope 92 Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half-life, 93 Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Two different methodologies based on extractive resins and LSC and ICP-MS techniques that enables the 93 Zr determination in medium (ILW) and low level (LLW) radioactive wastes samples from Brazilian nuclear power plants has been developed in our laboratory. Analyzing real samples 65% and 75% chemical yields for 93 Zr recovery were achieved for ICP-MS and LSC techniques, respectively. The detection limits were 0.045 μg.L -1 for ICP-MS and 0.05 Bq.L -1 for LSC techniques. (author)

  3. Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Radulescu, Georgeta; Mueller, Don; Goluoglu, Sedat; Hollenbach, Daniel F; Fox, Patricia B

    2007-01-01

    The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform postclosure criticality calculations. The validation process applies the criticality analysis methodology approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report. The application systems for this validation consist of waste packages containing transport, aging, and disposal canisters (TAD) loaded with commercial spent nuclear fuel (CSNF) of varying assembly types, initial enrichments, and burnup values that are expected from the waste stream and of varying degree of internal component degradation that may occur over the 10,000-year regulatory time period. The criticality computational tool being evaluated is the general-purpose Monte Carlo N-Particle (MCNP) transport code. The nuclear cross-section data distributed with MCNP 5.1.40 and used to model the various physical processes are based primarily on the Evaluated Nuclear Data File/B Version VI (ENDF/B-VI) library. Criticality calculation bias and bias uncertainty and lower bound tolerance limit (LBTL) functions for CSNF waste packages are determined based on the guidance in ANSI/ANS 8.1-1998 (Ref. 4) and ANSI/ANS 8.17-2004 (Ref. 5), as described in Section 3.5.3 of Ref. 1. The development of this report is consistent with Test Plan for: Range of Applicability and Bias Determination for Postclosure Criticality. This calculation report has been developed in support of licensing activities for the proposed repository at Yucca Mountain, Nevada, and the results of the calculation may be used in the criticality evaluation for CSNF waste packages based on a conceptual TAD canister.

  4. Turnover of amyloid precursor protein family members determines their nuclear signaling capability.

    Science.gov (United States)

    Gersbacher, Manuel T; Goodger, Zoë V; Trutzel, Annette; Bundschuh, Diana; Nitsch, Roger M; Konietzko, Uwe

    2013-01-01

    The amyloid precursor protein (APP) as well as its homologues, APP-like protein 1 and 2 (APLP1 and APLP2), are cleaved by α-, β-, and γ-secretases, resulting in the release of their intracellular domains (ICDs). We have shown that the APP intracellular domain (AICD) is transported to the nucleus by Fe65 where they jointly bind the histone acetyltransferase Tip60 and localize to spherical nuclear complexes (AFT complexes), which are thought to be sites of transcription. We have now analyzed the subcellular localization and turnover of the APP family members. Similarly to AICD, the ICD of APLP2 localizes to spherical nuclear complexes together with Fe65 and Tip60. In contrast, the ICD of APLP1, despite binding to Fe65, does not translocate to the nucleus. In addition, APLP1 predominantly localizes to the plasma membrane, whereas APP and APLP2 are detected in vesicular structures. APLP1 also demonstrates a much slower turnover of the full-length protein compared to APP and APLP2. We further show that the ICDs of all APP family members are degraded by the proteasome and that the N-terminal amino acids of ICDs determine ICD degradation rate. Together, our results suggest that different nuclear signaling capabilities of APP family members are due to different rates of full-length protein processing and ICD proteasomal degradation. Our results provide evidence in support of a common nuclear signaling function for APP and APLP2 that is absent in APLP1, but suggest that APLP1 has a regulatory role in the nuclear translocation of APP family ICDs due to the sequestration of Fe65.

  5. Determination of the working voltage of the RP-0 and RP-10 nuclear reactors starting chains

    International Nuclear Information System (INIS)

    Zuniga, Agustin; Veramendi, Emilio; Salazar, Alberto

    2014-01-01

    This report presents the determination of the voltage curve of the RP-0 and RP-10 nuclear reactor starting chains, as an approach for determining the working voltages. The method consisted in changing the voltage and recording the corresponding counts. Then, the area of the best response was determined according to the detector characteristics, and also was found that for the RP-0, the response was in the proportional region, meanwhile for the RP-10, the response was in the region of ionization chambers. The values obtained were: BF3-A3 (RP-0) and 1150 V for RP-10, CF-A1 = 400 V, CF-A2 = 400 V, CF-A3 = 400 V. (authors).

  6. Determination of 90Sr in waters of discharge of nuclear power plants

    International Nuclear Information System (INIS)

    Campos, J.M.; Equillor, H.E.

    2010-01-01

    The determination of 90 Sr has some problems because it is a pure beta emitter, and despite the specificity of radiochemical techniques used, their full identification is not always easy, especially when detected low activities. In addition, samples water discharge presents a matrix consisting of a series of fission or activation products, beta / gamma emitters, several of which may interfere with the determination of 90 Sr. This paper describes a simple method for the determination of 90 Sr in water of discharge of nuclear power plants, which is based on the purification of 90 Y, which is used in the ARN since 2009 and has yielded good results to the present, as no interferences were detected in the analysis of the decay of 90 Y. (authors) [es

  7. Procedure, algorithm and criterions of determination of a burnup of a irradiated nuclear fuel in process of overloading

    International Nuclear Information System (INIS)

    Bilej, D.V.; Fridman, N.A.; Maslov, O.V.; Maksimov, M.V.

    2001-01-01

    The procedure, algorithm and criterions of determination of a burnup of the irradiated nuclear fuel in process of overloading are described. The feature of the procedure, algorithm and criterions consists in the account of initial enrichment and cooling time nuclear fuel after irradiation

  8. The GRP1 PH domain, like the AKT1 PH domain, possesses a sentry glutamate residue essential for specific targeting to plasma membrane PI(3,4,5)P(3).

    Science.gov (United States)

    Pilling, Carissa; Landgraf, Kyle E; Falke, Joseph J

    2011-11-15

    During the appearance of the signaling lipid PI(3,4,5)P(3), an important subset of pleckstrin homology (PH) domains target signaling proteins to the plasma membrane. To ensure proper pathway regulation, such PI(3,4,5)P(3)-specific PH domains must exclude the more prevalant, constitutive plasma membrane lipid PI(4,5)P(2) and bind the rare PI(3,4,5)P(3) target lipid with sufficiently high affinity. Our previous study of the E17K mutant of the protein kinase B (AKT1) PH domain, together with evidence from Carpten et al. [Carpten, J. D., et al. (2007) Nature 448, 439-444], revealed that the native AKT1 E17 residue serves as a sentry glutamate that excludes PI(4,5)P(2), thereby playing an essential role in specific PI(3,4,5)P(3) targeting [Landgraf, K. E., et al. (2008) Biochemistry 47, 12260-12269]. The sentry glutamate hypothesis proposes that an analogous sentry glutamate residue is a widespread feature of PI(3,4,5)P(3)-specific PH domains, and that charge reversal mutation at the sentry glutamate position will yield both increased PI(4,5)P(2) affinity and constitutive plasma membrane targeting. To test this hypothesis, we investigated the E345 residue, a putative sentry glutamate, of the general receptor for phosphoinositides 1 (GRP1) PH domain. The results show that incorporation of the E345K charge reversal mutation into the GRP1 PH domain enhances PI(4,5)P(2) affinity 8-fold and yields constitutive plasma membrane targeting in cells, reminiscent of the effects of the E17K mutation in the AKT1 PH domain. Hydrolysis of plasma membrane PI(4,5)P(2) releases the E345K GRP1 PH domain into the cytoplasm, and the efficiency of this release increases when Arf6 binding is disrupted. Overall, the findings provide strong support for the sentry glutamate hypothesis and suggest that the GRP1 E345K mutation will be linked to changes in cell physiology and human pathologies, as demonstrated for AKT1 E17K [Carpten, J. D., et al. (2007) Nature 448, 439-444; Lindhurst, M. J., et al

  9. Radiometric determination of density of fresh shielding concrete (in situ) in the nuclear industry

    International Nuclear Information System (INIS)

    Honig, A.

    1985-01-01

    Methods of radiometric determination of density have been in recent years elaborated in detail and successfully. But on the market no instruments are available for measuring fresh concrete when it is possible to repair inhomogeneities, if any, even before hardening, and thus to guarantee safety of biological protection of nuclear reactors. The paper describes an analog and digital radiation density meter and their application in the inspection of radiation protection concrete walls. By repairing defective, insufficiently dense locations still in the course of concrete placement it is possible to attain a laboratory quality of the concrete even under on-site conditions

  10. Determination of elements in industrial waste sample and TENORM using XRF Technique in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Paulus, W.; Sarimah Mahat; Meor Yusoff Meor Sulaiman

    2011-01-01

    Industrial waste such as aluminium dross and TENORM waste, oil sludge has been used as sample in this research. Determination of main elements by using X-Ray Fluorescence (XRF) in Material Technology Group, Malaysian Nuclear Agency. Results shows that main elements in these samples, aluminium and silicon, respectively. Thereby, this research shows that XRF can be considered as one of the techniques that can be used in waste characterization and furthermore, it can help researchers and engineer in the research related to waste treatment especially radioactive waste. (author)

  11. On experimental determination of characteristics of nuclear fusion reactions from mu-molecular resonance states

    International Nuclear Information System (INIS)

    Bystritskij, V.M.; Pen'kov, F.M.

    1997-01-01

    Charge-nonsymmetrical deuterium-helium muon complexes (dμHe) are studied. A method is proposed for experimentally determining the rates of nuclear fusion reactions in dμHe molecules in the J=1 and J=0 states (J is the orbital moment of the system) and the partial rates for radiative decay of these complexes in these states. Experiments are supposed to be carried out at meson factories with gaseous and cryogenic targets filled with a mixture of deuterium and helium

  12. System for determining the local power in the fuel assembly of a nuclear reactor

    International Nuclear Information System (INIS)

    Rolstad, Erik; Korpas, T.-H.; Leyse, R.H.; Smith, R.D.

    1979-01-01

    System for determining the local power in the fuel assembly of a nuclear reactor which includes a rod conducting the heat and electricity, along which axial areas act as a gamma radiation thermometer. Each area includes a thermal bridge, a cold source and a pair of junctions acting as thermocouples so placed that they measure the temperature difference between the thermal bridge and the cold source. The power created by the fuel assembly near each area acting as gamma thermometer is found from this difference in temperature [fr

  13. Strontium and calcium determination in sea fishes in neighborhood of Angra nuclear power plant

    International Nuclear Information System (INIS)

    Ferreira, L.M.J.

    1985-01-01

    Strontium-90 is an important radionuclide present in the liquid effluents of the Angra Nuclear Power Plant, located in the coastline of Rio de Janeiro State. It has a long effective half-life, easy entry into food chain due to its chemical similarity to calcium and stays for a long time in solution. With the aim of calculating the concentration factor (CF) for 90 Sr and observed ratio (OR) in the most abundant local fish, it was determined the strontium and calcium content in the edible fraction of nine species and in sea water by atomic absorption spectrophotometry. (author)

  14. Determination of chlorine in nuclear-grade uranium compounds by ion-selective electrode

    International Nuclear Information System (INIS)

    Yang Chunqing; Liu Fuyun; Huang Dianfan.

    1989-01-01

    The determination of microamount chlorine in nuclear-grade uranium compounds is described. Chlorine is separated from uranium oxide pyrohydrolytically with stream of wet oxygen in a furnace at 800-900 deg C. Chlorine is volatilized as hydrochloric acid, which then is absorbed in a dilute alkaline solution and measured with chlorine selective electrode. This method covers the concentration range of 10-500 ppm chlorine in uranium oxide. The relative standard diviation is better than 10% and recovery of 85-108% has been reported

  15. A set of enhanced green fluorescent protein concatemers for quantitative determination of nuclear localization signal strength.

    Science.gov (United States)

    Böhm, Jennifer; Thavaraja, Ramya; Giehler, Susanne; Nalaskowski, Marcus M

    2017-09-15

    Regulated transport of proteins between nucleus and cytoplasm is an important process in the eukaryotic cell. In most cases, active nucleo-cytoplasmic protein transport is mediated by nuclear localization signal (NLS) and/or nuclear export signal (NES) motifs. In this study, we developed a set of vectors expressing enhanced GFP (EGFP) concatemers ranging from 2 to 12 subunits (2xEGFP to 12xEGFP) for analysis of NLS strength. As shown by in gel GFP fluorescence analysis and αGFP Western blotting, EGFP concatemers are expressed as fluorescent full-length proteins in eukaryotic cells. As expected, nuclear localization of concatemeric EGFPs decreases with increasing molecular weight. By oligonucleotide ligation this set of EGFP concatemers can be easily fused to NLS motifs. After determination of intracellular localization of EGFP concatemers alone and fused to different NLS motifs we calculated the size of a hypothetic EGFP concatemer showing a defined distribution of EGFP fluorescence between nucleus and cytoplasm (n/c ratio = 2). Clear differences of the size of the hypothetic EGFP concatemer depending on the fused NLS motif were observed. Therefore, we propose to use the size of this hypothetic concatemer as quantitative indicator for comparing strength of different NLS motifs. Copyright © 2017 Elsevier Inc. All rights reserved.

  16. Determination of leveled costs of electric generation for gas plants, coal and nuclear; Determinacion de costos nivelados de generacion electrica para plantas de gas, carbon y nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G.; Palacios H, J.C.; Ramirez S, J.R.; Gomez, A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: galonso@nuclear.inin.mx

    2005-07-01

    The present work analyzes the leveled costs of electric generation for different types of nuclear reactors known as Generation III, these costs are compared with the leveled costs of electric generation of plants with the help of natural gas and coal. In the study several discount rates were used to determine their impact in the initial investment. The obtained results are comparable with similar studies and they show that it has more than enough the base of the leveled cost the nuclear option it is quite competitive in Mexico. Also in this study it is also thinks about the economic viability of a new nuclear power station in Mexico. (Author)

  17. Climate change benefits and energy supply benefits as determinants of acceptance of nuclear power stations: Investigating an explanatory model

    International Nuclear Information System (INIS)

    Visschers, Vivianne H.M.; Keller, Carmen; Siegrist, Michael

    2011-01-01

    Several countries are currently discussing whether they will rebuild their nuclear power stations in order to continue this type of energy production in the future. The public, with its own opinion about nuclear power stations, has an influential voice in this discussion. As a result, policy makers and nuclear scientists are interested in the public's perception of nuclear power and in what determines this perception. We therefore examined an explanatory model of the public's acceptance of nuclear power based on a telephone survey among a representative sample in Switzerland. The model included such factors as risk perception, benefit perception, affective feelings, and social trust. Moreover, we distinguished between two types of benefit perception: benefit for the climate and a secure energy supply. The model fitted very well to our data and explained acceptance very well. Acceptance was mainly influenced by perceived benefits for a secure energy supply and, to a lesser extent, both by perceived benefits for the climate and by risk perception. Affective feelings about nuclear power appeared to be a central factor in the model. Implications for communication about nuclear power stations and for further research are discussed. - Highlights: → Explanatory model of determinants of nuclear power acceptance was studied in the representative survey. → Perceived benefits for a secure energy supply had the largest influence on acceptance. → Perceived benefits for the climate seemed less influential on acceptance. → Affect had a central role in the explanatory model. → Implications for communication about nuclear power plants are discussed.

  18. Climate change benefits and energy supply benefits as determinants of acceptance of nuclear power stations: Investigating an explanatory model

    Energy Technology Data Exchange (ETDEWEB)

    Visschers, Vivianne H.M., E-mail: vvisschers@ethz.ch [ETH Zurich, Institute for Environmental Decisions (IED), Consumer Behavior, Universitaetsstrasse 22 CHN J 75.2, 8092 Zurich (Switzerland); Keller, Carmen; Siegrist, Michael [ETH Zurich, Institute for Environmental Decisions (IED), Consumer Behavior, Universitaetsstrasse 22 CHN J 75.2, 8092 Zurich (Switzerland)

    2011-06-15

    Several countries are currently discussing whether they will rebuild their nuclear power stations in order to continue this type of energy production in the future. The public, with its own opinion about nuclear power stations, has an influential voice in this discussion. As a result, policy makers and nuclear scientists are interested in the public's perception of nuclear power and in what determines this perception. We therefore examined an explanatory model of the public's acceptance of nuclear power based on a telephone survey among a representative sample in Switzerland. The model included such factors as risk perception, benefit perception, affective feelings, and social trust. Moreover, we distinguished between two types of benefit perception: benefit for the climate and a secure energy supply. The model fitted very well to our data and explained acceptance very well. Acceptance was mainly influenced by perceived benefits for a secure energy supply and, to a lesser extent, both by perceived benefits for the climate and by risk perception. Affective feelings about nuclear power appeared to be a central factor in the model. Implications for communication about nuclear power stations and for further research are discussed. - Highlights: > Explanatory model of determinants of nuclear power acceptance was studied in the representative survey. > Perceived benefits for a secure energy supply had the largest influence on acceptance. > Perceived benefits for the climate seemed less influential on acceptance. > Affect had a central role in the explanatory model. > Implications for communication about nuclear power plants are discussed.

  19. Nuclear Criticality Calculation for Determining the Bach Size in a Pyroprocessing Facility

    International Nuclear Information System (INIS)

    Ko, Won Il; Lee, Ho Hee; Chang, Hong Rae; Song, Dae Yong; Kwon, Eun Ha; Jung, Chang Jun; Yoon, Suk Kyun

    2009-01-01

    The criticality analysis in a pyroprocessing facility is very important element for the R and D and the facility design in terms of the determination of batch size of the sub-processes as well as facility safety. Particularly, the determining the batch size is essential at the beginning stage of the R and D. In this report, the criticality analysis was carried out for the subprocesses such as voloxidation, electrolytic reduction, electrorefining and electrowinning process in order to estimate the maximum batch size of each process by using Monte Carlo code (MCNP4/C2). On the whole, the criticality problem could not give a big effect on the batch sizes in the voloxidation, electrolytic reduction and electrorefining. However, it was resulted that permissible amount of nuclear material to prevent the criticality accident in the electrowinning process was about 10kgHM

  20. Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Grison, J [Compagnie Generale des Matieres Nucleaires (COGEMA), Centre de la Hague, 50 - Cherbourg (France)

    1980-10-01

    The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis.

  1. Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Grison, J.

    1980-01-01

    The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis [fr

  2. Idaho Nuclear Technology and Engineering Center (INTEC) Sodium Bearing Waste - Waste Incidental to Reprocessing Determination

    International Nuclear Information System (INIS)

    Jacobson, Victor Levon

    2002-01-01

    U.S. Department of Energy Manual 435.1-1, Radioactive Waste Management, Section I.1.C, requires that all radioactive waste subject to Department of Energy Order 435.1 be managed as high-level radioactive waste, transuranic waste, or low-level radioactive waste. Determining the radiological classification of the sodium-bearing waste currently in the Idaho Nuclear Technology and Engineering Center Tank Farm Facility inventory is important to its proper treatment and disposition. This report presents the technical basis for making the determination that the sodium-bearing waste is waste incidental to spent fuel reprocessing and should be managed as mixed transuranic waste. This report focuses on the radiological characteristics of the sodium-bearing waste. The report does not address characterization of the nonradiological, hazardous constituents of the waste in accordance with Resource Conservation and Recovery Act requirements

  3. Spectrophotometric determination of zirconium with Chrome Azurol s in aqueous streams of nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Ganesh, S.; Velavendan, P.; Pandey, N.K.; Kamachi Mudali, U.; Natarajan, R.

    2014-01-01

    A sensitive and reproducible spectrophotometric method for the determination of zirconium is developed. The method is based on the formation of stable bluish violet colour complex with Chrome Azurol S (CAS) with maximum absorption at 598 nm. The complex formed obeys Beer's law in the range of 1-7 μg/mL. Under optimum conditions, the sensitivity of the proposed method, (i.e. the detection limit), molar absorptivity and Sandell's sensitivity values are 2.42 μg/mL, 3.93 x10 3 L.Mol -1 .cm -1 and 2.54 x 10 -4 μg/cm 2 respectively. Relative standard deviation is less than 2% and correlation coefficient is 0.997. The present method is highly sensitive, selective, rapid and simple. It can be applied for the direct determination of zirconium in environmental, industrial, water and nuclear reprocessing samples. (author)

  4. Determination of moisture in black coal using pulsed nuclear magnetic resonance spectrometry

    International Nuclear Information System (INIS)

    Cutmore, N.G.; Sowerby, B.D.; Lynch, L.J.; Webster, D.S.

    1987-01-01

    Pulsed nuclear magnetic resonance (n.m.r.) spectrometry was investigated as a technique for moisture determination in fine product coal from eight Australian coal washeries. Measurements were made on samples of diameter 8 and 12 mm and length 10 and 120 mm at frequencies from 6.5 to 60 MHz. The ratio of intensities of the water and coal components in the free-induction decay signal can be used to determine moisture to within approx. 0.4-0.7 wt% over the range 0-26 wt% moisture, independent of sample density. This accuracy is independent of particle size (up to 1 mm) and little affected by coal rank, sample length or n.m.r. frequency. (author)

  5. Nuclear Criticality Calculation for Determining the Bach Size in a Pyroprocessing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il; Lee, Ho Hee; Chang, Hong Rae; Song, Dae Yong; Kwon, Eun Ha; Jung, Chang Jun; Yoon, Suk Kyun [KAERI, Daejeon (Korea, Republic of)

    2009-01-15

    The criticality analysis in a pyroprocessing facility is very important element for the R and D and the facility design in terms of the determination of batch size of the sub-processes as well as facility safety. Particularly, the determining the batch size is essential at the beginning stage of the R and D. In this report, the criticality analysis was carried out for the subprocesses such as voloxidation, electrolytic reduction, electrorefining and electrowinning process in order to estimate the maximum batch size of each process by using Monte Carlo code (MCNP4/C2). On the whole, the criticality problem could not give a big effect on the batch sizes in the voloxidation, electrolytic reduction and electrorefining. However, it was resulted that permissible amount of nuclear material to prevent the criticality accident in the electrowinning process was about 10kgHM

  6. Nuclear techniques for determining biomass production, evaporation and transpiration, root development and nutritional value

    International Nuclear Information System (INIS)

    Niemann, E.G.; Kuehn, W.; Kaul, A.K.

    1975-01-01

    From the Institute of Radiation Botany, Hanover, some nuclear methods are presented which could be of assistance to the plant breeders in selecting for positive plant characters. Several methods have been developed for the continuous determination of biomass by means of gamma-absorption measurements in single plants as well as in experimental field plots. The response of plant growth to environmental conditions such as fertilization, irrigation, and day length, dependent on genetic parameters can easily be followed by these techniques. Primarily for the investigation of water vapour movement in soils and between soil and atmosphere under conditions of temperature inversions, a technique has been worked out using 3 H-labelled water and water vapour. The inclusion of plants in this system will allow the determination of water balance under varying environmental conditions. An autoradiographic method has been applied using 86 Rb as trace element mainly for the measurement of root distribution of trees (apple, coffee). Finally, a sequence of analytical steps are described that have been developed and used in Hanover for the selection for protein amount and quality in crop plants. Though not all of these steps include nuclear methods, the application of tracer techniques in this and other screening sequences is an invaluable help for breeders and analysts. (author)

  7. Determination of nuclear spins of short-lived isotopes by laser induced fluorescence

    International Nuclear Information System (INIS)

    Buchinger, F.; Dabkiewicz, P.; Kremmling, H.; Kuehl, T.; Mueller, A.C.; Schuessler, H.A.

    1980-01-01

    The spins of several nuclear ground and isomeric states have been measured for a number of mercury isotopes. The fluorescent light from the 6s6p 3 P 1 state is observed at 2537 Angstroem after excitation with the frequency doubled output of a pulsed dye laser. Four different laser induced fluorescence techniques were tested for their applicability: double resonance, Hanle effect, time delayed integral Hanle beats, and time resolved quantum beats. The sensitivity and selectivity of these models are compared with emphasis on the determination of spins of nuclei far from beta-stability, where short half lives and low production yields restrict the number of available atoms. The experiments were carried out on-line with the ISOLDE isotope separator at CERN at densities as low as 10 6 atoms/cm 3 . Results for the very neutron deficient high spin mercury isomers with half lives of several seconds, but also for the ground states of the abundant low spin stable mercury isotopes, are given as examples. The test measurements determined the nuclear spins of the odd sup(185m-191m)Hg isomers to be I = 13/2. (orig.)

  8. A study on determinants of risk perception and attitude structures concerning nuclear power technology

    International Nuclear Information System (INIS)

    Tsuchida, Shoji; Kitada, Atsuko; Ato, Kazunori

    2000-01-01

    attitude structures, in order to manage the risks of mega-technologies, especially the risk of nuclear technology. Social surveys on people's attitudes toward nuclear power plants carried out in Japan showed that cognition of necessity and safety of them and fear of them had strong effects on the attitudes, and that the female had more negative attitudes than the male, and that people on administrative positions by occupation had most affirmative attitudes. However, there are few social survey researches that focus on the people's tendencies to zero-risk perception or comparative-risk perception to clarify the nature and determinants of attitude structures toward nuclear power technology. In this presentation we try to point out the factors which should be considered to manage the risks of mega-technologies in the social decision making processes by describing the survey data of zero-risk perception, comparative-risk perception, and over-sensibility to hazards relating to the attitude structures toward nuclear power technology. (author)

  9. Determination of Kr-85 in environmental samples and gaseous effluents from nuclear industries using the standard method

    International Nuclear Information System (INIS)

    Heras Iniquez, M.C.; Perez Garcia, M.M.

    1983-01-01

    The determination of the Kr-85 activity in environmental samples and gaseous effluents from Spanish Nuclear Power Stations is described. The method employed has been published elsewhere. The determinations has been carried out in environmental samples token at JEN Laboratories (Madrid) and the Nuclear Power Stations, Jose Cabrera (Zorita), Garona and Vandellos. Also samples of gaseous effluents of the three plants has been analyzed. Values of the Kr-85 environmental background activity in the Almaraz Nuclear Power Stations, has been determined, before the beginning of its nuclear activity. In this paper the sampling equipment used is described and the values found of Kr-85 activity in all the samples in given. (Author) 29 refs

  10. Determination of scutellarin in breviscapine preparations using quantitative proton nuclear magnetic resonance spectroscopy

    Directory of Open Access Journals (Sweden)

    Zhenzuo Jiang

    2016-04-01

    Full Text Available The objective of the present study was to develop the selection criteria of proton signals for the determination of scutellarin using quantitative nuclear magnetic resonance (qNMR, which is the main bioactive compound in breviscapine preparations for the treatment of cerebrovascular disease. The methyl singlet signal of 3-(trimethylsilylpropionic-2,2,3,3-d4 acid sodium salt was selected as the internal standard for quantification. The molar concentration of scutellarin was determined by employing different proton signals. To obtain optimum proton signals for the quantification, different combinations of proton signals were investigated according to two selection criteria: the recovery rate of qNMR method and quantitative results compared with those obtained with ultra-performance liquid chromatography. As a result, the chemical shift of H-2′ and H-6′ at δ 7.88 was demonstrated as the most suitable signal with excellent linearity range, precision, and recovery for determining scutellarin in breviscapine preparations from different manufacturers, batch numbers, and dosage forms. Hierarchical cluster analysis was employed to evaluate the determination results. The results demonstrated that the selection criteria of proton signals established in this work were reliable for the qNMR study of scutellarin in breviscapine preparations.

  11. Determination of uranium from nuclear fuel in environmental samples using inductively coupled plasma mass spectrometry

    International Nuclear Information System (INIS)

    Boulyga, S.F.; Becker, J.S.

    2000-01-01

    As a result of the accident at the Chernobyl nuclear power plant (NPP) the environment was contaminated with spent nuclear fuel. The 236 U isotope was used in this study to monitor the spent uranium from nuclear fallout in soil samples collected in the vicinity of the Chernobyl NPP. A rapid and sensitive analytical procedure was developed for uranium isotopic ratio measurement in environmental samples based on inductively coupled plasma quadrupole mass spectrometry with a hexapole collision cell (HEX-ICP-QMS). The figures of merit of the HEX-ICP-QMS were studied with a plasma-shielded torch using different nebulizers (such as an ultrasonic nebulizer (USN) and Meinhard nebulizer) for solution introduction. A 238 U + ion intensity of up to 27000 MHz/ppm in HEX-ICP-QMS with USN was observed by introducing helium into the hexapole collision cell as the collision gas at a flow rate of 10 ml min -1 . The formation rate of uranium hydride ions UH + /U + of 2 x 10 -6 was obtained by using USN with a membrane desolvator. The limit of 236 U/ 238 U ratio determination in 10 μg 1 -1 uranium solution was 3 x 10 -7 corresponding to the detection limit for 236 U of 3 pg 1 -1 . The precision of uranium isotopic ratio measurements in 10 μg 1 -1 laboratory uranium isotopic standard solution was 0.13% ( 235 U/ 238 U) and 0.33% ( 236 U/ 238 U) using a Meinhard nebulizer and 0.45% ( 235 U/ 238 U) and 0.88% ( 236 U/ 238 U) using a USN. The isotopic composition of all investigated Chernobyl soil samples differed from those of natural uranium; i.e. in these samples the 236 U/ 238 U ratio ranged from 10 -5 to 10 -3 . (orig.)

  12. Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

    International Nuclear Information System (INIS)

    Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

    1979-01-01

    The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

  13. Nuclear magnetic resonance spectroscopy for determining the functional content of organic aerosols: A review

    International Nuclear Information System (INIS)

    Chalbot, Marie-Cecile G.; Kavouras, Ilias G.

    2014-01-01

    The knowledge deficit of organic aerosol (OA) composition has been identified as the most important factor limiting our understanding of the atmospheric fate and implications of aerosol. The efforts to chemically characterize OA include the increasing utilization of nuclear magnetic resonance spectroscopy (NMR). Since 1998, the functional composition of different types, sizes and fractions of OA has been studied with one-dimensional, two-dimensional and solid state proton and carbon-13 NMR. This led to the use of functional group ratios to reconcile the most important sources of OA, including secondary organic aerosol and initial source apportionment using positive matrix factorization. Future research efforts may be directed towards the optimization of experimental parameters, detailed NMR experiments and analysis by pattern recognition methods to identify the chemical components, determination of the NMR fingerprints of OA sources and solid state NMR to study the content of OA as a whole. - Highlights: • Organic aerosol composition by 1 H- and 13 C-NMR spectroscopy. • NMR fingerprints of specific sources, types and sizes of organic aerosol. • Source reconciliation and apportionment using NMR spectroscopy. • Research priorities towards understanding organic aerosol composition and origin. - This review presents the recent advances on the characterization of organic aerosol composition using nuclear magnetic resonance spectroscopy

  14. A nuclear DNA-based species determination and DNA quantification assay for common poultry species.

    Science.gov (United States)

    Ng, J; Satkoski, J; Premasuthan, A; Kanthaswamy, S

    2014-12-01

    DNA testing for food authentication and quality control requires sensitive species-specific quantification of nuclear DNA from complex and unknown biological sources. We have developed a multiplex assay based on TaqMan® real-time quantitative PCR (qPCR) for species-specific detection and quantification of chicken (Gallus gallus), duck (Anas platyrhynchos), and turkey (Meleagris gallopavo) nuclear DNA. The multiplex assay is able to accurately detect very low quantities of species-specific DNA from single or multispecies sample mixtures; its minimum effective quantification range is 5 to 50 pg of starting DNA material. In addition to its use in food fraudulence cases, we have validated the assay using simulated forensic sample conditions to demonstrate its utility in forensic investigations. Despite treatment with potent inhibitors such as hematin and humic acid, and degradation of template DNA by DNase, the assay was still able to robustly detect and quantify DNA from each of the three poultry species in mixed samples. The efficient species determination and accurate DNA quantification will help reduce fraudulent food labeling and facilitate downstream DNA analysis for genetic identification and traceability.

  15. Determination of velocity and flow direction of ground water by using nuclear techniques

    International Nuclear Information System (INIS)

    Santos Ferreira, L. dos.

    1976-06-01

    The dynamics of water in an aquifer with the purpose of determining the filtration velocity and the direction of groundwater flow with radioactive tracers was studied. Field equipment for the purposes of the study was built in the Laboratory of Tracers in Hydrology in collaboration with the Institute of Nuclear Engineering (IEN/NUCLEBRAS). The equipment was designed to minimize the possible vertical flows, loss and molecular diffusion of the tracer out of the studied region. The performance of the nuclear detectors and the constructional details of the field equipament were examined. The selection of the radioactive tracers was made taking into account its availibility and radiation facilities, cost of the inactive material and their physical and chemical properties. The tracers used were 82 Br and 198 Au. The results are discussed with the help of auxiliary informations such as plots of water levels in time and space, profiles and grain analysis. In order to obtain a physical explanation of the results, a qualitative model of the flow in the aquifer is also presented. (Author) [pt

  16. Nuclear assay of coal. Volume 4. Moisture determination in coal: survey of electromagnetic techniques. Final report

    International Nuclear Information System (INIS)

    Bevan, R.; Luckie, P.; Gozani, T.; Brown, D.R.; Bozorgmanesh, H.; Elias, E.

    1979-01-01

    This survey consists of two basic parts. The first consists of a survey of various non-nuclear moisture determination techniques. Three techniques are identified as promising for eventual on-line application with coal; these are the capacitance, microwave attenuation, and nuclear magnetic resonance (NMR) techniques. The second part is devoted to an in-depth analysis of these three techniques and the current extent to which they have been applied to coal. With a given coal type, accuracies of +- 1% absolute in moisture content are achievable with all three techniques. The accuracy of the two electromagnetic techniques has been demonstrated in the laboratory and on-line in coal burning plants, whereas only small samples have been analyzed with NMR. The current shortcoming of the simple electromagnetic techniques is the sensitivity of calibrations to physical parameters and coal type. NMR is currently limited by small sample sizes and non-rugged design. These findings are summarized and a list of manufacturers of moisture analyzers is given in the Appendix

  17. Nuclear Test Depth Determination with Synthetic Modelling: Global Analysis from PNEs to DPRK-2016

    Science.gov (United States)

    Rozhkov, Mikhail; Stachnik, Joshua; Baker, Ben; Epiphansky, Alexey; Bobrov, Dmitry

    2016-04-01

    Seismic event depth determination is critical for the event screening process at the International Data Center, CTBTO. A thorough determination of the event depth can be conducted mostly through additional special analysis because the IDC's Event Definition Criteria is based, in particular, on depth estimation uncertainties. This causes a large number of events in the Reviewed Event Bulletin to have depth constrained to the surface making the depth screening criterion not applicable. Further it may result in a heavier workload to manually distinguish between subsurface and deeper crustal events. Since the shape of the first few seconds of signal of very shallow events is very sensitive to the depth phases, cross correlation between observed and theoretic seismograms can provide a basis for the event depth estimation, and so an expansion to the screening process. We applied this approach mostly to events at teleseismic and partially regional distances. The approach was found efficient for the seismic event screening process, with certain caveats related mostly to poorly defined source and receiver crustal models which can shift the depth estimate. An adjustable teleseismic attenuation model (t*) for synthetics was used since this characteristic is not known for most of the rays we studied. We studied a wide set of historical records of nuclear explosions, including so called Peaceful Nuclear Explosions (PNE) with presumably known depths, and recent DPRK nuclear tests. The teleseismic synthetic approach is based on the stationary phase approximation with hudson96 program, and the regional modelling was done with the generalized ray technique by Vlastislav Cerveny modified to account for the complex source topography. The software prototype is designed to be used for the Expert Technical Analysis at the IDC. With this, the design effectively reuses the NDC-in-a-Box code and can be comfortably utilized by the NDC users. The package uses Geotool as a front-end for data

  18. Statistical evaluation of the analytical method involved in French nuclear glasses leaching rate determination

    Energy Technology Data Exchange (ETDEWEB)

    Broudic, V.; Marques, C.; Bonnal, M

    2004-07-01

    Chemical durability studies of nuclear glasses involves a large number of water leaching experiments at different temperatures and pressures on both, glasses doped with fission products and actinides and non radioactive surrogates. The leaching rates of these glasses are evaluated through ICPAES analysis of the leachate over time. This work presents a statistical evaluation of the analysis method used to determine the concentrations of various vitreous matrix constituents: Si, B, Na, Al, Ca, Li as major elements and Ba, Cr, Fe, Mn, Mo, Ni, P, Sr, Zn, Zr as minor elements. Calibration characteristics, limits of detection, limits of quantification and uncertainties quantification are illustrated with different examples of analysis performed on surrogates and on radioactive leachates in glove box. (authors)

  19. Determination of nuclear fuel burnup by non-destructive gamma spectroscopy

    International Nuclear Information System (INIS)

    Soares, A.J.

    1979-01-01

    The determination of nuclear fuel burnup by the non-destructive gamma spectroscopy method is studied. A MTR (Materials Testing Reactor) -type fuel element is used in the measurement. The fuel element was removed from the reactor core in 1958 and, because of the long decay time, show only one peak in is gamma spectrum at 661.6 Kev. Corresponding to 137 Cs. Measurements are made at 330 points of the element using a Nal detector and the final result revealed that the quantity of 235 U consumed was 3.3 +- 0,8 milligram in the entire element. The effect of the migration of 137 Cs in the element is neglected in view of the fact that it occurs only when the temperature is above 1000 0 C, which is not the case in IEAR-1. (Author)

  20. Nuclear-physical techniques for determination of boron distribution in pure materials

    International Nuclear Information System (INIS)

    Kadirova, M.; Jumaev, N.; Simakhin, Yu.F.; Idrisov, Kh.; Usmanova, M.M.

    2001-01-01

    To study deep boron diffusion in the complex silicon structures, consisting of interchange boron doping layers of mono- and polycrystalline silicon, separated by oxide films a technique of sidelong section by using Solid State Nuclear Track Detector (SSNTD) has been elaborated. The boron distribution determination technique is based on the detection of alpha particles from the 10B(n, )7Li reaction with cellulose nitrate film. The etched track registering cellulose nitrate film show the structure image magnified 1/sin fold. Boron concentration defined by density of the etched pits appearing on the film surface. An optical microscope analysis of the sample track-mapping image is realized by examination with closely spaced ( l < x/sin ) and largely spaced ( l x/sin ) movements. All these elaborated techniques can be used to investigate other solid matrix

  1. Determination of 17 impurity elements in nuclear quality uranium compounds by atomic absorption spectroscopy

    International Nuclear Information System (INIS)

    Andonie, O.; Smith, L.A.; Cornejo, S.

    1985-01-01

    A method is described for the determination of 17 elements (Al, Ca, Cd, Co, Cr, Cu, Fe, K, Li, Mg, Mn, Mo, Na, Ni, Pb, V and Zn) in the ppm level, in nuclearly pure uranium compounds by flame atomic absorption spectroscopy. The analysis is performed by first dissolving the uranium sample in nitric acid and then extracting the uranium with tributyl phosphate solution. The aqueous phase, free of uranium, which contains the elements to analyze is inspirated into the flame of an atomic absorption spectrophotometer using air-acetylene or nitrous oxide-acetylene flame according to the element in study. This method allows to extract the uranium selectively in more than 99.0% and the recovery of the elements sudied was larger 90% (for K) to 100% (for Cr). The sensitivity of the method vary from 0.096 μg/g U (for Cd) to 5.5 μg/g U (for Na). (Author)

  2. Determination of free acidity in nuclear fuel reprocessing streams by fiber optic aided spectrophotometric technique

    International Nuclear Information System (INIS)

    Ganesh, S.; Velavendan, P.; Pandey, N.K.; Kamachi Mudali, U.; Natarajan, R.

    2014-01-01

    A fiber optic aided spectrophotometric technique has been developed for the determination of free acidity in nuclear fuel reprocessing streams. The developed method is simple, accurate and applicable to all ranges of nitric acid and heavy metal concentrations relevant to the purex process. The method is based on the formation of yellow colour with an acid-sensitive indicator such as chrome azurol s, the intensity of yellow colour is proportional to the acid concentration. The system obeys Lambert-Beer's law at 455 nm in the range of acidity 1-10 M of nitric acid. The results obtained are reproducible with standard deviation 2% and relative error is less than 3%. The results obtained by the developed technique are in good agreement with those obtained by the standard procedure. This method is adaptable for remote operation and on-line monitoring. (author)

  3. Development of high performance liquid chromatography for rapid determination of burn-up of nuclear fuels

    International Nuclear Information System (INIS)

    Joseph, M.; Karunasagar, D.; Saha, B.

    1996-01-01

    Burn-up an important parameter during evaluation of the performance of any nuclear fuel. Among the various techniques available, the preferred one for its determination is based on accurate measurement of a suitable fission product monitor and the residual heavy elements. Since isotopes of rare earth elements are generally used as burn-up monitors, conditions were standardized for rapid separation (within 15 minutes) of light rare earths using high performance liquid chromatography based on either anion exchange (Partisil 10 SAX) in methanol-nitric acid medium or by cation exchange on a reverse phase column (Spherisorb 5-ODS-2 or Supelcosil LC-18) dynamically modified with 1-octane sulfonate or camphor-10-sulfonic acid (β). Both these methods were assessed for separation of individual fission product rare earths from their mixtures. A new approach has been examined in detail for rapid assay of neodymium, which appears promising for faster and accurate measurement of burn-up. (author)

  4. Determination of chemical forms of 14C in liquid discharges from nuclear power plants.

    Science.gov (United States)

    Svetlik, I; Fejgl, M; Povinec, P P; Kořínková, T; Tomášková, L; Pospíchal, J; Kurfiřt, M; Striegler, R; Kaufmanová, M

    2017-10-01

    Developments of radioanalytical methods for determination of radiocarbon in wastewaters from nuclear power plants (NPP) with pressurized light water reactors, which would distinguish between the dissolved organic and inorganic forms have been carried out. After preliminary tests, the method was used to process pilot samples from wastewater outlets from the Temelín and Dukovany NPPs (Czech Republic). The results of analysis of pilot water samples collected in 2015 indicate that the instantaneous 14 C releases into the water streams would be about 7.10 -5 (Temelín) and 4.10 -6 (Dukovany) of the total quantity of the 14 C liberated into the environment. Copyright © 2017 Elsevier Ltd. All rights reserved.

  5. Determination of trace metals in nuclear-grade uranium dioxide by X-ray fluorescence spectrometry

    International Nuclear Information System (INIS)

    Salvador, V.L.R.; Imakuma, K.

    1988-04-01

    A method is described for the simultaneous determination of low concentrations of Ca, Cr, Cu, Fe, Mn and Ni in nuclear-grade uranium dioxide by X-ray fluorescence spectrometry, without the use of chemical treatment. The lower limits of detection range from 2 μg g -1 for nickel and manganese to 5 μg g -1 for copper. Samples are prepared in the form of double-layer pellets with boric acid as a binding agent. Standards are prepared in a U 3 O 8 matrix, which is more chemically stable than UO 2 and has similar matrix behaviour. The correlation coefficients for calibration curves are better than 0.999. Erros range from 2.4 % for chromium to 6.8 % for nickel. (author) [pt

  6. Determination of the lowest critical power levels of the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Huy, Ngo Quang [Centre for Nuclear Technique Application, Ho Chi Minh City (Viet Nam); Thong, Ha Van; Long, Vu Hai; Binh, Do Quang; Nghiem, Huynh Ton; Tuan, Nguyen Minh; Vien, Luong Ba; Vinh, Le Vinh [Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    This paper presents the experimental methods for determining critical states of the Dalat Nuclear Research Reactor containing an extraneous neutron source induced by gamma ray reactions on beryllium in the reactor. The lowest critical power levels are measured at various moments after the reactor is shut down following 100 hours of its continuous operation. Th power levels vary from (0.5-1.2) x 10{sup -4} of P{sub n}, i.e. (25-60)W to (1.1-1.6) x 10{sup -5} of P{sub n}, i.e. (5.5-8)W at corresponding times of 4 days to 13 days after the reactor is shut down. However the critical power must be chosen greater than 500 W to sustain the steady criticality of the reactor for a long time. (author). 3 refs. 4 figs. 1 tab.

  7. Statistical evaluation of the analytical method involved in French nuclear glasses leaching rate determination

    International Nuclear Information System (INIS)

    Broudic, V.; Marques, C.; Bonnal, M.

    2004-01-01

    Chemical durability studies of nuclear glasses involves a large number of water leaching experiments at different temperatures and pressures on both, glasses doped with fission products and actinides and non radioactive surrogates. The leaching rates of these glasses are evaluated through ICPAES analysis of the leachate over time. This work presents a statistical evaluation of the analysis method used to determine the concentrations of various vitreous matrix constituents: Si, B, Na, Al, Ca, Li as major elements and Ba, Cr, Fe, Mn, Mo, Ni, P, Sr, Zn, Zr as minor elements. Calibration characteristics, limits of detection, limits of quantification and uncertainties quantification are illustrated with different examples of analysis performed on surrogates and on radioactive leachates in glove box. (authors)

  8. Measuring head for determining the pressure of fission gases released inside bars of nuclear fuel

    International Nuclear Information System (INIS)

    Granata, S.

    1984-01-01

    A measuring head suitable for determining the pressure of fission gases released inside non-instrumented bars of nuclear fuel (which have reached high irradiation levels), and for connection to said bars by a method which allows no escape of said active gases and does not cause appreciable disturbance either to the fuel or to the released fission gases, is disclosed. The head consists of a tubular casing adapted to be welded at one end to the bar, and having a metal bellows at its other end. A pointed metal bar is used to penetrate the bar by a blow to a pin, whereupon pressure variations within the casing are measured by a pressure measuring device having an iron core, the movement of the core, due to such pressure variations, being recorded by a differential transformer. (author)

  9. Application of dynamic and transition magnetic fields for determination of magnetic moments of short-lived nuclear states

    International Nuclear Information System (INIS)

    Burgov, N.A.

    1986-01-01

    Problem of measuring magnetic momenta of short-living nuclear states is discussed. Different methods for measuring magnetic momenta using interionic and transient magnetic fields were considered. Possibility for determining a value g by means of measuring correlation attenuation is investigated as well as measuring magnetic momenta by means of inclined foils. At present 2 + level magnetic momenta for many odd-odd nuclei have been determined by means of the above methods. The methods are only ones for determining magnetic momenta of nuclear levels with small lifetimes up to tenth and hundredth of shares of picoseconds

  10. Determination of a Wear Initiation Cycle by using a Contact Resistance Measurement in Nuclear Fuel Fretting

    International Nuclear Information System (INIS)

    Lee, Young Ho; Kim, Hyung Kyu

    2008-01-01

    In nuclear fuel fretting, the improving of the contact condition with a modified spring shape is a useful method for increasing the wear resistance of the nuclear fuel rod. This is because the fretting wear resistance between the fuel rod and grid spring is mainly affected by the grid spring shape rather than the environment, the contact modes, etc. In addition, the wear resistance is affected by the wear debris behavior between contact surfaces. So, it is expected that the wear initiation of each spring shape should be determined in order to evaluate a wear resistance. However, it is almost impossible to measure the wear behavior in contact surfaces on a real time basis because the contact surfaces are always hidden. Besides, the results of the worn surface observation after the fretting wear tests are restricted to archive the information on the wear debris behavior and the formation mechanism of the wear scar. In order to evaluate the wear behavior during the fretting wear tests, it is proposed that the contact resistance measurement is a useful method for examining the wear initiation cycle and modes. Generally, fretting wear damages are rapidly progressed by a localized plastic deformation between the contact surfaces, crack initiation and fracture of the deformed surface with a strain hardening difference between a surface and a subsurface and finally a detachment of wear debris. After this, wear debris is easily oxidized by frictional heat, test environment, etc. At this time, a small amount of electric current applied between the contact surfaces will be influenced by the wear debris, which could be an obstacle to an electric current flow. So, it is possible to archive the information on the wear behavior by measuring the contact resistance. In order to determine the wear initiation cycle during the fretting wear tests, in this study, fretting wear tests have been performed by applying a constant electric current in room temperature air

  11. Determination of burnup in irradiated nuclear fuels by the method of stable 148Nd fission products

    International Nuclear Information System (INIS)

    Souza Sarkis, J.E. de.

    1982-01-01

    A method is described for the isotopic analysis and determination of burnup in irradiated nuclear fuel by mass spectrometric technique. The burnup is calculed from the determination of the concentration of uranium, plutonium and the fission product 148 Nd in the samples of UO 2 irradiated fuel from a P.W.R. type reactor. The method involves the separation of fractions of uranium, plutonium and neodimium from the dissolved irradiated fuel by ion exchange technique. The determination of uranium, plutonium and the fission product 148 Nd is carried out by isotope diluition mass spectrometry technique using as isotope tracers the nuclides 233 U, 242 Pu and 150 Nd. For the chemical processing and handling of the irradiated sample a Hot Chemistry Laboratory was mounted. It consists of glove boxes and equipments for radiation monitoring and protection. The results obtained indicate an atom percent burnup of 2.181 + - 0.035% wich corresponds an 20.937 + - 0.739 Gwd/ton of thermal energy produced. (Author) [pt

  12. Calibration factor determination for solid nuclear track detectors CR-39 type exposed to Rn-222

    International Nuclear Information System (INIS)

    Cazula, Camila Dias; Campos, Marcia Pires de; Mazzilli, Barbara Paci

    2014-01-01

    In the detection method with solid nuclear track detector, when a heavy particle rests on the detector surface, causes a breakdown in their molecular structure forming a trace. One of the typical applications of these detectors is the measurement of the concentration of Rn -222 in air, a noble radioactive gas, part of the U-238 series, emitting alpha particles and important in epidemiological studies to protect individuals from natural radiation. To determine the concentration of Rn -222 in the air in a room is necessary to know the density of lines (traces / cm 2 ) on the detector surface, the exposure time and the calibration factor. The determination of the calibration factor for CR-39 detectors was taken from the exposure of these to a known concentration of Rn-222. Therefore, the detectors were placed inside a cell of Lucas adapted and subsequently exposed to a concentration of Rn-222 15 kBq / m 3 , by means of the apparatus RN-150 Pylon Electronics Incorporation, which has a source of Ra-226 and releases known concentrations of Rn-222. Six calibration factor determinations were performed, the average value obtained was 0.0534 ±0.0021 (traces / cm 2 per Bq / m 3 day). The results are consistent with literature values for the same type of detector and showed good reproducibility

  13. Determination of radiochemistry purity and pH of radiopharmaceutical in Northeast nuclear medicine services

    International Nuclear Information System (INIS)

    Andrade, Wellington; Santos, Poliane; Lima, Fernando de Andrade; Lima, Fabiana Farias de

    2013-01-01

    The radiopharmaceutical is a chemical compound associated with a radionuclide, which is selected so that meets the need cf diagnosis and capable of producing quality images. Drugs labeled with 99m Tc radionuclide kits consist of lyophilized, and be handled by the nuclear medicine services (NMS) must pass tests as the resolution of ANVISA (RDC 38) published in 2008. Among these tests are those of radiochemical purity and pH determination. This study evaluated the radiochemical purity of radiopharmaceuticals and pH SMN manipulated in the Northeast. The radiochemical purity (RCP) was determined by thin layer chromatography, which were used Whatman ® and silica gel, with dimensions of 1 x 10 cm, as stationary phase, and solvents indicated in the inserts of manufacturers. The chromatographic strips were placed in sealed containers so as not to touch the walls thereof. After the chromatographic run, the tape was cut every centimeter and the activities determined in doses of each calibrator NMS. The pH of the radiopharmaceutical was assessed through the use of universal pH paper (Merck®) and obtained staining compared with its color scale. The results showed (hat 82.6% and 100% of the radiopharmaceuticals of the samples were within the limits recommended by international pharmacopoeias for radiochemical purity and pl-l, respectively. There is then the need to include in routine tests indicated SMN by ANVISA. Well, they can detect possible problems in the marking of radiopharmaceuticals administered to the patient and avoid inappropriate material. (author)

  14. Determination of NAPL contamination and evolution of remediation by means nuclear techniques

    International Nuclear Information System (INIS)

    Balcazar, M.; Pena, P.; Lopez, A.; Flores, J. H.; Villegas, D.; Schubert, M.; Knoller, K.

    2008-01-01

    In this work the application of two nuclear techniques is presented: Natural radioactive tracer and stable isotopics tracer, that allow the localization and delimitation of the contamination in ground and underground water for hydrocarbons denominated NAPL. The work was carry out on the whole and with access permission to facilities and technical information, in a storage center and distribution of fuel of hydrocarbons where occurred a spill for hydrocarbons, approaching actions of remediation that allow to the date to fulfill the normative one applicable. By means of measurement of 222 Rn, in situ, it was possible to be related its ground concentration to the degree of contamination previously determined; the evaluation of 222 Rn in underground water in group with the determination of stable isotope δ 34 S, δ 18 O and δ 13 C as well as the dissolved inorganic coal allowed to locate the contamination source in underground water to 100 m of depth in the aquifer and to determine the existence of a natural bioremediation. (Author)

  15. U.S. nuclear non-proliferation policy: impact on exports and nuclear industry could not be determined. Report to the Congress

    International Nuclear Information System (INIS)

    1980-01-01

    The Nuclear Non-Proliferation Act of 1978 established new measures to prevent the diversion to weapons use of peaceful nuclear exports. It also created a policy to confirm U.S. reliability as a nuclear supplier. GAO did not identify any export sales lost as a result of the Act, but did find indications that nonproliferation policies can influence export sales. Based on available data, GAO could not determine the impact of the Act on the competitiveness of U.S. nuclear exports. However, U.S. companies are at some disadvantage because importers perceive that implementation of the Act may result in delayed export licenses. The United States dominated the nuclear export market through the early 1970s. However, foreign competitors, some aided by U.S. technology transfers, emerged to monopolize home markets and compete for third-country business. Further, the market has been depressed since 1974 and prospects for U.S. nuclear power plant exports have dimmed greatly. However, U.S. companies continue to view exports as important to sustain production capacity

  16. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  17. A nuclear-medical method applied for determining the choledochus diameter after cholecystectomy

    International Nuclear Information System (INIS)

    Wolf, M.

    1980-01-01

    54 patients (46 of them females, 8 males) who underwent cholecystectomy at least 4 years ago, were followed up roentgenologically by infusion cholangiography and nuclear-medicinally by quantitative hepatobiliary functional scintiscanning (HBFS). The ROI method applied for HBFS permits to record time/activity curves above the liver parenchyma (A) and the porta of the liver (B). By substracting curve A of curve B with the scale in which A is incorporated in B, a curve B' results, indicating the flow volume through the porta of the liver. The quotient Q=maximum pulse A to B/maximum pulse B to B indicates the portion of the liver parenchyma in the porta curve. The quotient represents a measure for the total volume of the large bile ducts included in the region of the porta of the liver. The quantity 1-Q/Q was put in relation with the roentgenologically determined common bile duct diameters. It resulted that both quantities correlated well, with a correlation coefficient of r=-0.860. Thus, the choledochus diameter can be determined in a primarily functional examination with a precision of 2 mm, a degree which permits the detection of clinically relevant discharge malfunctions. It was not possible to detect peristalsis-dependent phenomena with a dosage of 4-5 mCi 99 mTc-diethyl-IDA, an irradiation dose which was sufficient for answering the clinical questions and could be justified for the patients. (orig.) [de

  18. Nuclear magnetism of liquid 3He: new determination of the Landau parameter F0a

    International Nuclear Information System (INIS)

    Goudon, V.

    2006-10-01

    He 3 is a liquid Fermi model, isotropic, with an attainable Fermi temperature and the interaction between atoms can be controlled by changing the pressure of the liquid. In this document, we present accurate NMR measurements of the nuclear magnetic susceptibility of liquid He 3 as a function of temperature and pressure. The emphasis has been placed on reliable thermometry and on He 3 pressure measurements directly in the cell to increase the measuring range until solidification, and an accurate characterization of the NMR spectrometer. Our measurements give an effective Fermi temperature 5% lower than former results. The Landau parameter F 0 a depends on the effective mass, which is determined by specific heat measurements, and consequently on the temperature scale. The re-analysis of the specific heat measurements with the PLTS-2000 temperature scale yields an effective mass increase of 4.5%. In this document, F 0 a is determined for 2 temperature scales (PLTS-2000 and Greywall). Contrarily to former measurements, the F 0 a density dependence does not show any saturation at high pressures. (author)

  19. Determination of a test section parameters for Iris nuclear reactor pressurizer

    International Nuclear Information System (INIS)

    Silva, Mario A.B. da; Lira, Carlos A.B. de O.

    2009-01-01

    An integral, modular and medium size nuclear reactor, known as IRIS, is being developed by Westinghouse and by research centers. IRIS is characterized by having most of its components inside the pressure vessel, eliminating the probability of accidents. Due to its integral configuration, there is no spray system for boron homogenization, which may cause power transients. Thus, boron mixing must be investigated. The aim of this paper is to establish the conditions under which a test section has to be built for boron dispersion analysis inside IRIS reactor pressurizer. Through Fractional Scaling Analysis, which is a new methodology of similarity, the main parameters for a test section are obtained. By combining Fractional Scaling Analysis with local scaling for the densimetric Froude number and a previously established volumetric scale factor, the values of recirculation orifices, inlet water temperature, time scale factor and recirculation flow for the test section (model) are determined so that boron distribution is well represented in IRIS reactor pressurizer (prototype). Analytical solutions were used to validate the adopted methodology and when the results simulated in the model are compared to those that characterize the prototype, the agreement for both systems is absolute. The thermal power also influences boron distribution inside the test section. This power is determined by condensation laws in the vapor region and by suitable correlations for free convection. The fractions for rising inlet recirculation water enthalpy and vapor formation are also considered. (author)

  20. Scaling factors for the activity determination of radioactive waste from nuclear power reactors

    International Nuclear Information System (INIS)

    Medici, Marcela A.; Piumetti, Elsa H.

    2007-01-01

    Specific information of the total activity and activity concentration of the radionuclides contained is required for conditioning, transporting and final disposal of radioactive waste. Due to the complexity associated to alpha and beta measurements for these emitters it is worldwide used, particularly in the case of heterogeneous radioactive waste, the Scaling Factor Method. As in other cases, inputs of the results of the analysis of waste samples taking from waste streams are necessary. The Scaling Factor Method is based on the determination of averaged correlations between the activity concentrations of Difficult to Measure (DTM) nuclides (i.e. alpha and beta emitters) and the activity concentration of easy to measure nuclides (i.e. strong gamma emitters) called Key Nuclides (KN). In the application of this method two phases may be identified: in the first one the degree of correlation between averaged activities of DTM and a given KN is verified, and specific Scaling Factors are derived for every DTM radionuclide. In the second stage the total activity and the activity concentration of the selected KN is determined in each waste item and, by applying the SFs obtained previously, the activities of DTM nuclides are calculated. It is concluded that this method is appropriate and cost-effective and it is stressed that it is only applicable while the Nuclear Power Reactor is in operation. (author)

  1. Determination of boron in Jabroc wood used as a shielding material in nuclear reactors

    International Nuclear Information System (INIS)

    Kamble, Granthali S.; Manisha, V.; Venkatesh, K.

    2015-01-01

    Jabroc are non-impregnated, densified wood laminates developed commercially for a wide range of industrial applications. Jabroc can be used with other neutron shielding materials such as Lead to form complex shielding structures. Its relative light weight and cleanliness in handling are additional features that make it a suitable candidate for the standard design of neutron shielding equipment. Jabroc can also be impregnated with Boron up to a maximum of 4% to be used in areas where Gamma radiation produced on Neutron capture reaches unacceptable dose rates. Boron impregnated Jabroc wood finds application in TAPS 3 and 4 as a shielding material for the Ion Chambers and the Horizontal Flux Units (HFU). The shielding property of this material is optimized by incorporating requisite amount of boron in wood. Boron content in this material has to be determined accurately prior to its use in the nuclear reactors. In this work a method was standardized to determine boron in Jabroc wood samples to check for conformance to specifications. The wood sample flakes were wetted with saturated barium hydroxide solution and dries under IR. The sample was ashed in a muffle furnace at 600℃ for 2 h

  2. Determination of uranium from nuclear fuel in environmental samples using inductively coupled plasma mass spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Boulyga, S.F. [Forschungszentrum Juelich GmbH (Germany). Zentralabteilung fuer Chemische Analysen]|[Radiation Physics and Chemistry Problems Inst., Minsk (Belarus); Becker, J.S. [Forschungszentrum Juelich GmbH (Germany). Zentralabteilung fuer Chemische Analysen

    2000-11-01

    As a result of the accident at the Chernobyl nuclear power plant (NPP) the environment was contaminated with spent nuclear fuel. The {sup 236}U isotope was used in this study to monitor the spent uranium from nuclear fallout in soil samples collected in the vicinity of the Chernobyl NPP. A rapid and sensitive analytical procedure was developed for uranium isotopic ratio measurement in environmental samples based on inductively coupled plasma quadrupole mass spectrometry with a hexapole collision cell (HEX-ICP-QMS). The figures of merit of the HEX-ICP-QMS were studied with a plasma-shielded torch using different nebulizers (such as an ultrasonic nebulizer (USN) and Meinhard nebulizer) for solution introduction. A {sup 238}U{sup +} ion intensity of up to 27000 MHz/ppm in HEX-ICP-QMS with USN was observed by introducing helium into the hexapole collision cell as the collision gas at a flow rate of 10 ml min{sup -1}. The formation rate of uranium hydride ions UH{sup +}/U{sup +} of 2 x 10{sup -6} was obtained by using USN with a membrane desolvator. The limit of {sup 236}U/{sup 238}U ratio determination in 10 {mu}g 1{sup -1} uranium solution was 3 x 10{sup -7} corresponding to the detection limit for {sup 236}U of 3 pg 1{sup -1}. The precision of uranium isotopic ratio measurements in 10 {mu}g 1{sup -1} laboratory uranium isotopic standard solution was 0.13% ({sup 235}U/{sup 238}U) and 0.33% ({sup 236}U/{sup 238}U) using a Meinhard nebulizer and 0.45% ({sup 235}U/{sup 238}U) and 0.88% ({sup 236}U/{sup 238}U) using a USN. The isotopic composition of all investigated Chernobyl soil samples differed from those of natural uranium; i.e. in these samples the {sup 236}U/{sup 238}U ratio ranged from 10{sup -5} to 10{sup -3}. (orig.)

  3. EDF's approach to determine specifications for nuclear power plant bulk chemicals

    International Nuclear Information System (INIS)

    Basile, Alix; Dijoux, Michel; Le-Calvar, Marc; Gressier, Frederic; Mole, Didier

    2012-09-01

    Chemical impurities in the primary, secondary and auxiliary nuclear power plants circuits generate risks of corrosion of the fuel cladding, steel and nickel based alloys. The PMUC (Products and Materials Used in plants) organization established by EDF intends to limit this risk by specifying maximum levels of impurities in products and materials used for the operation and maintenance of Nuclear Power Plants (NPPs). Bulk chemicals specifications, applied on primary and secondary circuit chemicals and hydrogen and nitrogen gases, are particularly important to prevent chemical species to be involved in the corrosion of the NPPs materials. The application of EDF specifications should lead to reasonably exclude any risk of degradation of the first and second containment barriers and auxiliary circuits Important to Safety (IPS) by limiting the concentrations of chlorides, fluorides, sulfates... The risk of metal embrittlement by elements with low melting point (mercury, lead...) is also included. For the primary circuit, the specifications intend to exclude the risk of activation of impurities introduced by the bulk chemicals. For the first containment barrier, to reduce the risk of deposits like zeolites, PMUC products specifications set limit values for calcium, magnesium, aluminum and silica. EDF's approach for establishing specifications for bulk chemicals is taking also into account the capacity of industrial production, as well as costs, limitations of analytical control methods (detection limits) and environmental releases issues. This paper aims to explain EDF's approach relative to specifications of impurities in bulk chemicals. Also presented are the various parameters taken into account to determine the maximum pollution levels in the chemicals, the theoretical hypothesis to set the specifications and the calculation method used to verify that the specifications are suitable. (authors)

  4. Determination of 18O by prompt nuclear reaction analysis: application for measurement of microsamples

    International Nuclear Information System (INIS)

    Bradshaw, S.D.; Cohen, D.; Katsaros, A.; Tom, J.; Owen, I.J.

    1987-01-01

    A method is described for the routine determination of 18 O concentrations in microsamples of biological fluids. The method utilizes the prompt nuclear reaction 18 O(p,α 0 ) 15 N, and 846-keV protons from a 3-MeV Van de Graaff Accelerator are focused on ∼2,000-Angstroem-thick Ta 2 O 5 targets prepared by anodic oxidation from 50-μl samples of water distilled from blood or other biological fluids. The broad cross section of the resonance peak for this nuclear reaction (47 keV) ensures high yields, especially at small reaction angles, and the high-energy α particles produced by the reaction (4 MeV) are readily separated from scattered protons by the use of an aluminized Mylar foil of suitable thickness. Background levels of 18 O (0.204 atom%) can be detected with run times of ∼5-8 min, and the sensitivity of the method is of the order of 0.05 atom%. Experimental error due to sample preparation was found to be 1.7%, and counting errors were close to theoretical limits so that total error was of the order of 2.5%. Duplicate samples were analyzed by use of the 18 O(p,α 0 ) 15 N reaction at Lucas Heights, Australia and the 18 O(p,n) 18 F reaction at the University of California, Los Angeles, and the agreement was excellent (y = 1.0123x - 0.0123, r = 0.991, P < 0.001). The theoretical limitations and the general applicability of the method in biological studies designed to estimate the rate of metabolism of free-ranging animals are also discussed. 24 refs., 2 tabs., 7 figs

  5. The Social Determinants of Attitudes towards Nuclear Energy:Examination for the Value Mediated Mechanism(Special Issue Dedicated to Professor SUZUKI Tomihisa)

    OpenAIRE

    阪口, 祐介

    2016-01-01

    Since the 2011 Fukushima Daiichi nuclear power plant accident, the negative opinion to nuclear power plant has increased and the political debates over the pros and cons of nuclear energy has been activated. This paper attempts to reveal empirically the social determinants of attitudes towards nuclear energy. We focus on generation, gender, and social stratification as the determinants, and examine for the value mediated mechanism. Previous researches have indicated that women tend to have ne...

  6. Determination of nitrogen in wheat flour through Activation analysis using Fast neutron flux of a Thermal nuclear reactor

    International Nuclear Information System (INIS)

    Ramirez G, T.

    1976-01-01

    In this work is done a technical study for determining Nitrogen (protein) and other elements in wheat flour Activation analysis, with Fast neutrons from a Thermal nuclear reactor. Initially it is given an introduction about the basic principles of the methods of analysis. Equipment used in Activation analysis and a brief description of the neutron source (Thermal nuclear reactor). The realized experiments for determining the flux form in the irradiation site, the half life of N-13 and the interferences due to the sample composition are included too. Finally, the obtained results by Activation and the Kjeldahl method are tabulated. (Author)

  7. Determination of 241Pu in nuclear waste slurries: a comparative study using LSC and ICP-MS.

    Science.gov (United States)

    Jäggi, M; Röllin, S; Alvarado, J A Corcho; Eikenberg, J

    2012-02-01

    (241)Pu was determined in slurry samples from a nuclear reactor decommissioning project at the Paul Scherrer Institute (Switzerland). To validate the results, the (241)Pu activities of five samples were determined by LSC (TriCarb and Quantulus) and ICP-MS, with each instrument at a different laboratory. In lack of certified reference materials for (241)Pu, the methods were further validated using the (241)Pu information values of two reference sediments (IAEA-300 and IAEA-384). Excellent agreement with the results was found between LSC and ICP-MS in the nuclear waste slurries and the reference sediments. Copyright © 2011 Elsevier Ltd. All rights reserved.

  8. Determination of radon-222 concentration in inside environments of the Instituto de Engenharia Nuclear, Brazil

    International Nuclear Information System (INIS)

    Gouvea, Vandir de Azevedo; Cardoso, Domingos d'Oliveira; Castro, Carlos Alberto Carvalho

    2000-01-01

    The gotten concentrations of radon-222 in the installations of the IEN had been determined using the active and passive methods. The active method consisted on the use of the alpha spectrometry with a portable equipment Tracerlab Instruments WLM- Plus. In the determination for the passive method, one used detectors of nuclear strokes of type LEXAN. The raised values had been gotten in the wastes deposit and its annexes, room of the press and laboratory of wastes handling. It was observed, in this sector, an instantaneous measure of alpha spectrometry, concentrations around 1000 Bq.m-3, which had over all to the function of storage, the sector, a great volume of natural radioactive materials, especially of radium-226. This determination was carried through in an extreme situation of ventilation zero, where the gates had been kept closed during the execution of the same one. It was observed, however, a considerable fall, with values ten times inferior, after to submit the environment to a ventilation forced by means of fans and exhaust fans. The results gotten in the alpha spectrometry had been confirmed by the detectors of strokes, over all in that it says respect ace trends of storage of the gas in environments little ventilated. Some suggestions had been made on procedures to be adopted, aiming at the security of the people in these environments. The other places studied in the IEN had been, the room of the Argonauta reactor, laboratories and caves of the Cyclotron, diverse laboratories of the sector of chemistry and rooms of staff. The present study it objectified the establishment of a methodology of inquiry of the radon in occupational areas, besides considering solutions for the minimization of the concentrations of the gas, in similar environments of work to the ones of the IEN

  9. Determination and use of scaling factors for waste characterization in nuclear power plants

    International Nuclear Information System (INIS)

    2009-01-01

    The management of radioactive waste requires knowledge of the amounts and concentrations of specific radionuclides in the waste. The particular radionuclides of interest or concern may vary according to the safety case or other requirements of the waste management facility and/or the regulations of the Member State. Many of the radionuclides important for long term management of the waste are difficult to measure (DTM) from the outside of a waste package. Identification and quantification of these DTM nuclides require methods that, in general, involve analysis of waste samples using complex radiochemical analysis to separate the various radionuclides for measurement. This method of direct measurement is generally not practical to employ for large numbers of waste packages or for many heterogeneous waste streams. An alternative approach that can be used in many cases is to exploit the relationship between some easy to measure (ETM) key nuclides, such as certain gamma emitters, and the DTM nuclides to derive information for the DTM nuclides of interest. The scaling factor (SF) method is such an approach that is widely used to evaluate these DTM nuclides. The SF method is based on developing a correlation between ETM and DTM nuclides. The activities of DTM nuclides in waste packages are then estimated by measuring the ETM nuclides based on gamma measurements from outside the package and applying the SFs to calculate the DTM activities. The international standard ISO 21238:2007 gives guidelines for the general methodology for empirically determining SFs to evaluate the radioactivity of DTM nuclides in low and intermediate level radioactive waste (LILW) packages. The objective of this report is to provide information on the international experience in the determination and use of SFs. This report shows actual examples of the ways in which SFs have been derived and applied in various Member States. Although the main focus of the ISO standard is on LILW from the operation

  10. Behavioral Determinants of Russian Nuclear State-Owned Enterprises in Central and Eastern European Region

    OpenAIRE

    Vlcek, Tomas; Jirusek, Martin

    2015-01-01

    Rosatom State Nuclear Corporation play a substantial role in the energy sector of the Central and Eastern European region and the behavioral characteristics of the company forms the basis of this article. Rosatom is positioned as the dominant provider of nuclear technology and fuel supplies to the region, in large part stemming from the Soviet legacy in CEE countries. Compounding this challenge, nuclear energy is one of the major sources of power generation in CEE. Given the long-time, near m...

  11. Determination of half life of tellurium isotopes: a proposal for the teaching of nuclear physics

    International Nuclear Information System (INIS)

    Ruivo, Julio C.; Zamboni, Cibele B.; Batista, Wagner F.

    2013-01-01

    This work aimed at the development of courseware for teaching nuclear physics, using experimental data of half-life measurement (T1/2) of Tellurium isotopes (A=127 and 131). The choice of Tellurium was established for providing nuclear data, which are fundamental in related investigations of nuclear structure and its use in various areas such as geochemistry, chemical and pharmaceutical industries, astrophysics etc. For evaluation of the proposal performance, the material was made available, bringing a lot of information about nuclear safety, production and storage of radioactive material and concepts of radioactive decay, subatomic particles, emission of gamma radiation, half-life, etc.

  12. Determination of half life of tellurium isotopes: a proposal for the teaching of nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Ruivo, Julio C.; Zamboni, Cibele B.; Batista, Wagner F., E-mail: julio.ruivo.costa@usp.br, E-mail: czamboni@ipen.br, E-mail: fisicawagner@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    This work aimed at the development of courseware for teaching nuclear physics, using experimental data of half-life measurement (T1/2) of Tellurium isotopes (A=127 and 131). The choice of Tellurium was established for providing nuclear data, which are fundamental in related investigations of nuclear structure and its use in various areas such as geochemistry, chemical and pharmaceutical industries, astrophysics etc. For evaluation of the proposal performance, the material was made available, bringing a lot of information about nuclear safety, production and storage of radioactive material and concepts of radioactive decay, subatomic particles, emission of gamma radiation, half-life, etc.

  13. Determining of the nuclear composition of primary cosmic rays from the experimental distributions of multiple muons in atmospheric showers

    International Nuclear Information System (INIS)

    Beshtoev, Kh.M.

    1993-01-01

    Various approaches are discussed for determining the nuclear composition of the primary cosmic radiation from the distributions of multiple muons. Results are presented of calculations of the distributions of multiple muons for A 1 , A 4 , A 14 , A 26 , A 56 nuclei for an infinite plane and for the underground scintillation telescope of the Institute for Nuclear Research of the Academy of Sciences of Russia.The most suitable technique for determination of the primary nuclear composition of cosmic rays from the distribution of multiple muons is shown to be the approximate solution of a set of N equations, in which the respective coefficients of the contributions of various nuclei A i (i=1-N) to the primary composition serve as variables, while the remaining parts of these equations are the distributions of multiple muons obtained experimentally. 7 refs.; 2 tabs

  14. Quantitative determination of Quarternary alicyclic carbon atoms in coal and oil using nuclear magnetic resonance /sup 13/C method

    Energy Technology Data Exchange (ETDEWEB)

    Afonina, T.V.; Kushnarev, D.F.; Randin, O.I.; Shishkov, V.F.; Kalabin, G.A.

    1986-09-01

    Possibility is indicated for utilizing nuclear magnetic resonance spectroscopy for quantitative determination of Quarternary aliphatic carbon atoms in heavy hydrocarbon fractions of oil and coal extracts. C/sub n/, CH, CH/sub 2/ and CH/sub 3/ content in coal and oil samples are determined and corresponding resonance lines are referred to individual structural fragments (on the basis of nuclear magnetic resonance /sup 13/C spectra) of known saturated hydrocarbons. Tests were carried out on chloroform extracts of Irsha-Borodinsk coal, Mungunsk coal and paraffin and cycloparaffin of Sivinsk oil (b.p. over 550 C) fractions. Nuclear magnetic resonance spectra were obtained using Burker WP 200 spectrometer (50.13 MHz frequency). Results of the tests are given. 11 references.

  15. Receptor activator of nuclear factor kappa B (RANK as a determinant of peri-implantitis

    Directory of Open Access Journals (Sweden)

    Rakić Mia

    2013-01-01

    Full Text Available Background/Aim. Peri-implantitis presents inflammatory process that affects soft and hard supporting tissues of osseointegrated implant based on inflammatory osteoclastogenesis. The aim of this study was to investigate whether receptor activator of nuclear factor kappa B (RANK concentrations in peri-implant crevicular fluid could be associated with clinical parameters that reflect inflammatory nature of peri-implantitis. Methods. The study included 67 patients, 22 with diagnosed peri-implantitis, 22 persons with healthy peri-implant tissues and 23 patients with periodontitis. Clinical parameters from each patient were recorded and samples of peri-implant/gingival crevicular fluid were collected for the enzyme-linked immunosorbent assay (ELISA analysis. Results. RANK concentration was significantly increased in samples from the patients with periimplantitis when compared to healthy implants (p < 0.0001, where the average levels were 9 times higher. At the same time RANK concentration was significantly higher in periimplantitis than in periodontitis sites (p < 0.0001. In implant patients pocket depths and bleeding on probing values were positively associated with high RANK concentrations (p < 0.0001. Conclusion. These results revealed association of increased RANK concentration in samples of periimplant/ gingival crevicular fluid with peri-implant inflammation and suggests that RANK could be a pathologic determinant of peri-implantitis, thereby a potential parameter in assessment of peri-implant tissue inflammation and a potential target in designing treatment strategies.

  16. Determination of the catalyst circulation rate in a FCC cold flow pilot unit using nuclear techniques

    International Nuclear Information System (INIS)

    Santos, Valdemir A. dos; Lima, Emerson A.O.

    2013-01-01

    Nuclear techniques of gamma transmission and radioactive tracer were used to estimate the catalyst circulation rate in a cold flow pilot plant unit of Fluid Catalytic Cracking (FCC). Catalyst circulation rate in a FCC unit, allow to determine operating conditions of the exchange catalyst and inlet data for fluid dynamic simulation computational program. The pilot unit was fabricated obeying geometrical parameters provided by the Petrobras Research Center (CENPES), based on hot pilot units to existing in that center. The cold flow pilot unit has a transfer line, two separation vessels flash type, a return column, a riser and a regenerator. The vertical sections as riser, return column, regenerator column and transfer line are made of transparent material (glass). The two separation vessels have bases with tapered cylindrical shapes and are made of steel plates. The riser is divided into four sections of different diameters (0.005 m, 0.010 m, 0.018 m and 0.025 m) and rising upwards, to simulate the increasing flow rate caused by the increase of volume with the increase of the number of moles due to molecules breakage. The radioactive tracer used was the catalyst itself (intrinsic tracer) irradiated by neutron activation, yielding the radioisotope 59 Fe. The velocity measurements were also obtained with aid of an electronic clock triggered by certain radiation levels across the two detectors. Besides estimates for the catalyst circulation rate was possible to identify the type of flow relative to the catalyst in return column. (author)

  17. Determination of welding parameters for execution of weld overlayer on PWR nuclear reactor nozzles

    International Nuclear Information System (INIS)

    Ribeiro, Gabriela M.; Lima, Luciana I.; Quinan, Marco A.; Schvartzman, Monica M.

    2009-01-01

    In the PWR reactors, nickel based dissimilar welds have been presented susceptibilities the stress corrosion (S C). For the mitigation the problem a deposition of weld layers on the external surface of the nozzle is an alternative, viewing to provoke the compression of the region subjected to S C. This paper presents a preliminary study on the determination of welding parameters to obtain these welding overlayers. Welding depositions were performed on a test piece welded with nickel 182 alloy, simulating the conditions of a nozzle used in a PWR nuclear power plant. The welding process was the GTAW (Gas Tungsten Arc Welding), and a nickel 52 alloy as addition material. The overlayers were performed on the base metals, carbon steel an stainless steel, changing the welding parameters and verifying the the time of each weld filet. After that, the samples were micro structurally characterized. The macro structures and the microstructures obtained through optical microscopy and Vickers microhardness are presented. The preliminary results make evident the good weld quality. However, a small weld parameters influence used in the base material microstructure (carbon steel and stainless steel). The obtained results in this study will be used as reference in the construction of a mock up which will simulate all the conditions of a pressurizer nozzle of PWR reactor

  18. Structure determination of human Lck unique and SH3 domains by nuclear magnetic resonance spectroscopy

    Directory of Open Access Journals (Sweden)

    Willbold Dieter

    2003-05-01

    Full Text Available Abstract Background Protein tyrosine kinases are involved in signal transduction pathways that regulate cell growth, differentiation, activation and transformation. Human lymphocyte specific kinase (Lck is a 56 kDa protein involved in T-cell- and IL2-receptor signaling. Three-dimensional structures are known for SH3, SH2 and kinase domains of Lck as well as for other tyrosine kinases. No structure is known for the unique domain of any Src-type tyrosine kinase. Results Lck(1–120 comprising unique and SH3 domains was structurally investigated by nuclear magnetic resonance spectroscopy. We found the unique domain, in contrast to the SH3 part, to have basically no defined structural elements. The solution structure of the SH3 part could be determined with very high precision. It does not show significant differences to Lck SH3 in the absence of the unique domain. Minor differences were observed to the X-ray structure of Lck SH3. Conclusion The unique domain of Lck does not contain any defined structure elements in the absence of ligands and membranes. Presence of the unique domain is not relevant to the three-dimensional structure of the Lck SH3 domain.

  19. Determination of trace uranium in human hair by nuclear track detection technique

    International Nuclear Information System (INIS)

    Chung, Yong Sam; Moon, Jong Hwa; En, Zinaida; Cho, Seung Yeon; Kang, Sang Hoon; Lee, Jae Ki

    2001-01-01

    The aim of this study is to describe a usefulness of nuclear analytical technique in assessing and comparing the concentration levels through the analysis of uranium using human hair sample in the field of environment. A fission track detection technique was applied to determine the uranium concentration in human hair. Hair samples were collected from two groups of people - a) workers not dealing with uranium directly, and b) workers possibly contaminated with uranium. The concentration of 235 U for the first group varied from <1 to 39 ng/g and the second group can be estimated up to the level of μg/g. Radiographs of heavy-duty work samples contained high dense 'hot spots' along a single hair. After washing in acetone and distilled water, external contamination was not totally removed. Insoluble uranium compounds were not completely washed out. The (n, f)-radiography technique, having high sensitivity, and capable of getting information on uranium content at each point of a single hair, is an excellent tool for environmental monitoring

  20. Spectrographic determination of metallic impurities in organic coolants for nuclear reactors; Determinacion espectrografica de impurezas metalicas en refrigerantes organicos para reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Martin Munoz, M; Alvarez Gonzalez, F

    1969-07-01

    A spectrochemical method for determining metallic impurities in organic coolants for nuclear reactors is given. The organic matter in solid samples is eliminated by controlled distillation and dry ashing in the presence of magnesium oxide as carrier. Liquid, samples are vacuum distillated. The residue is analyzed by carrier distillation and by total burning techniques. The analytical results are discussed and compared with those obtained destroying the organic matter without carrier and using the copper spark technique. (Author) 12 refs.

  1. The mutual diffusion coefficient for (meth)acrylate monomers as determined with a nuclear microprobe

    International Nuclear Information System (INIS)

    Leewis, Christian M.; Mutsaers, Peter H.A.; Jong, Arthur M. de; Ijzendoorn, Leo J. van; Voigt, Martien J.A. de; Ren, Min Q.; Watt, Frank; Broer, Dirk J.

    2004-01-01

    The value of the mutual diffusion coefficient D V of two acrylic monomers is determined with nuclear microprobe measurements on a set of polymer films. These films have been prepared by allowing the monomers to diffuse into each other for a certain time and subsequently applying fast ultraviolet photo-polymerization, which freezes the concentration profile. The monomer diffusion profiles are studied with a scanning 2.1 MeV proton microprobe. Each monomer contains a marker element, e.g., Cl and Si, which are easily detected with proton induced x-ray emission. From the diffusion profiles, it is possible to determine the mutual diffusion coefficient. The mutual diffusion coefficient is dependent of concentration, which is concluded from the asymmetry in the Cl- and Si-profiles. A linear dependence of the mutual diffusion coefficient on the composition is used as a first order approximation. The best fits are obtained for a value of b=(0.38±0.15), which is the ratio of the diffusion coefficient of 1,3-bis(3-methacryloxypropyl)-1, 1,3,3-tetramethyldisiloxane in pure 2-chloroethyl acrylate and the diffusion coefficient of 2-chloroethyl acrylate in pure 1,3-bis(3-methacryloxypropyl)-1,1,3,3-tetramethyldisiloxane. Under the assumption of a linear dependence of the mutual diffusion coefficient D V on monomer composition, it follows that D V =(2.9±0.6)·10 -10 m 2 /s at a 1:1 monomer ratio. With Flory-Huggins expressions for the monomer chemical potentials, one can derive approximate values for the individual monomer diffusion coefficients

  2. The determination of trace element changes in Downer Cow Syndrome by nuclear methods

    International Nuclear Information System (INIS)

    Popescu, Ion V.; Iordan, M.; Dima, Gabriel; Stihi, Claudia; Oros, C.; Badica, Teodor

    2000-01-01

    Various biomedical applications of nuclear methods (especially Particle Induced X-Ray Emission PIXE) were developed in an extensive study by Johansson and Campbell.The causes of Downer Cow Syndrome (DCS) are the metabolic and toxic perturbation. The DCS is included in the largest group of dismineralisations with some other diseases of cattle like hypomagnesaemia. It is precisely a disease generated by the superposition of some factors. One of them is the type and the chemical composition of soil and plants involved in nutrition. Other factors are the chemical processes used in food preparation as well as some technological factors like: the husbandry system and the characteristics of the locally habitation and individual factors (the species, the productive type and physiological state). The origin of this syndrome is uncertain but the clinical experience indicates that the DCS is enhanced by the hypocalcaemic paresis of parturition. The diminution of some nutritive elements from food can be a cause of DCS. The cattle are more sensitive to the diminution of P in food in comparison to the diminution of Ca. An increase of this ratio determines unfortunately the Ca absorption because of the deficit of vitamin D. In the present study the elemental and enzymatic content of blood serum samples collected from cattle that are interesting from medical reasons was determined. The results obtained in pathological animals are compared with the normal data and with literature data for similar samples obtained from healthy cattle. Blood samples are collected from jugular zone of 30 cattle. Each serum sample was divided into three samples in order to make analyses by three methods (PIXE, Inductively Coupled Plasma and spectrometry using Bessey-Lowry method). (authors)

  3. General discrimination technique to determine between earthquake and nuclear test with seismic data

    International Nuclear Information System (INIS)

    Bashillah Baharuddin; Alawiah Musa; Roslan Mohd Ali

    2007-01-01

    The Comprehensive Nuclear-Test-Ban Treaty (CTBT) was developed to ban of any nuclear weapon test explosion moreover will restrict the development and qualitative improvement of nuclear weapons and end the development of advanced new types of these weapons. The Treaty provides for a comprehensive global verification regime, which includes an International Monitoring System (IMS). The IMS comprises a network of 321 monitoring stations and 16 radionuclide laboratories that monitor the Earth for evidence of nuclear explosions, which cover underground, underwater and atmosphere environments. Presently, Malaysia receives seismic, infrasound, hydroacoustic and radionuclide data from the International Data Centre (IDC) of the CTBT. In order to maximise the use of the data for the purposes of the CTBT, the Malaysian Nuclear Agency is developing capability to analyse the data in order to detect nuclear weapon test, with an initial focus on the seismic data. Through the CTBT IMS, seismic data is constantly being obtained to monitor and detect nuclear explosions. However, in the process, other natural and man-made activities that generate seismic waves, especially earthquakes and large man-made explosions, are also detectable through the IMS, and need to be differentiated and discriminated before any nuclear explosions can be identified. The detection capability by using seismological methods was proven through simulated explosion tests at selected nuclear weapon test sites. This is supported by data previously collected from a total of 2089 nuclear weapon tests that have been carried out globally, out of which 1567 were underground, 514 in the atmosphere, including outer space, and 8 underwater. The discrimination of seismic data to detect nuclear explosions from natural earthquake and explosions can be undertaken through the identification of the epicentre location, hypocentre depth, magnitude and short-period discrimination of the seismic events. (Author)

  4. Polarographic determination of Iodide and Iodate, in Solutions Coming from Aerosols in Fission Products Containment Studies in Nuclear Power Stations

    International Nuclear Information System (INIS)

    Sanchez, M.; Ballesteros, O.; Fernandez, M.; Clavero, M.A.; Gonzalez, A.M.

    2000-01-01

    A polarographic method is described for the iodine species determination, iodide and iodate in water solutions. the iodate can be determined by differential pulse polarography. Calibration curves and the detection and determination limits have been obtained. Iodides is oxidized to iodate with sodium hypochlorite and the excess of oxidizing agent is destroyed with sodium sulphide. The concentration of iodide is calculated as the difference between the concentration of iodate in the sample before and after the oxidation. As an application, species of iodine in samples coming from the experimental plants GIRS (Gaseous Iodine Removal by Sprays) of Nuclear Fission Department of the CIEMAT, dedicated to fission products containment studies in nuclear power station, were determined. (Author) 10 refs

  5. Activity determination for neutron dosimetry in the vigilance programme for the pressure vessel in Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    Furnari, J.C.; Cohen, I.M.; Ciriani, D.F.; Helzel Garcia, J.

    1993-01-01

    The methodologies for the activity determination of Co-60, Nb-93m and Nb-94 in flux monitors are presented. This was done in order to evaluate dose and damage caused by radiation received by pressure vessel materials of the Atucha I nuclear power plant for its surveillance program. (author)

  6. Determination of water fluoride levels in the vicinities of the nuclear fuel plant in Resende, Rio de Janeiro

    International Nuclear Information System (INIS)

    Carneiro, L.A.; Castro Faria, M.V. de

    1983-01-01

    The water fluoride levels in rivers and lakes, in a total of 26 different collection points placed within a circle of 10 km in diameter having the Nuclear Fuel Plant of Resende, Rio de Janeiro, as the center, were determined. (E.G.) [pt

  7. Investigation into the possibility of using short silver half-lives for the determination of silver in nuclear emulsions

    International Nuclear Information System (INIS)

    Guazzoni, P.; Laverlochere, M.; Heilmann, C.; Jung, M.; Francois, H.

    1982-01-01

    The 24 s and 2.4 mn short halft-life Ag 110 and Ag 108 isotopes were used to determine the quantity of silver remaining in developed nuclear emulsions after exposure to various neutron and gamma radiations. The test carried out should lead to the development and construction of automatic measurement equipment [fr

  8. Determination of gaseous radionuclide forms in the stack air of nuclear power plants

    Czech Academy of Sciences Publication Activity Database

    Tecl, J.; Světlík, Ivo

    2009-01-01

    Roč. 67, č. 5 (2009), s. 950-952 ISSN 0969-8043 Institutional research plan: CEZ:AV0Z10480505 Keywords : Nuclear-energy facilities * radioactive noble gases * 14C Subject RIV: DL - Nuclear Waste, Radioactive Pollution ; Quality Impact factor: 1.094, year: 2009

  9. Costs of construction, operation and maintenance of nuclear power plants - determinant factors

    International Nuclear Information System (INIS)

    Silva, R.A. da

    1981-01-01

    A study about the construction costs of the Angra-1 nuclear power plant, including direct costs, equipment costs, installation and indirect costs such as: engineering, job-training and administration is presented. The operation and maintenance costs of the Angra-1 nuclear power plant and costs of energy generation are still studied. (E.G.) [pt

  10. Expressing determination: From ENS programme 'Women and nuclear energy' to WIN

    Energy Technology Data Exchange (ETDEWEB)

    Heininen-Ojanperae, Marke [Information Officer, Imatran Voima Oy (Finland)

    1993-07-01

    WIN is an international association of women working professionally in the fields of nuclear energy and radiation application and willing to devote time to public information. It is established as non-profit making. WIN'S working language is English. WIN aims to contribute to objectively informing the public, especially women, on nuclear energy and radiation, in particular by: meeting regularly to exchange ideas and experiences between countries' WIN information groups, establishing country WIN groups in nuclear countries as widely as practical, supporting each other across borders, working out shared information techniques and information materials for international use. WIN is open to female nuclear and radiation professionals and academics as well as communications specialists, from all over the world, pledged to adhere to the goals of this Charter. The first WINFO Quarterly Newsletter of Women in Nuclear has been published.

  11. The determination of 99Tc by ICP-MS in samples collected near nuclear installations

    International Nuclear Information System (INIS)

    Ihsanullah; East, B.W.

    1991-01-01

    99 Tc occurs naturally in the earth's crust primarily from spontaneous fission of 238 U and slow neutron-induced fission of 235 U. 99 Tc is also produced from nuclear detonation tests, nuclear fuel processing plants and nuclear power stations. By comparison to other sources, the contribution to 99 Tc from natural sources and use of 99m Tc in medicine is considered to be negligible. Releases of 99 Tc from the nuclear fuel cycle include reactor operation, nuclear fuel reprocessing, UF 6 conversion, uranium enrichment, U fuel fabrication, high-level waste solidification, low and high-level waste disposal; however the main contribution to the release of 99 Tc is the process of uranium enrichment. Various environmental samples from the Irish Sea and from Chernobyl have been analysed for 99 Tc by newly developed procedures using the inductively coupled plasma mass spectrometry technique. (author)

  12. Expressing determination: From ENS programme 'Women and nuclear energy' to WIN

    International Nuclear Information System (INIS)

    Heininen-Ojanperae, Marke

    1993-01-01

    WIN is an international association of women working professionally in the fields of nuclear energy and radiation application and willing to devote time to public information. It is established as non-profit making. WIN'S working language is English. WIN aims to contribute to objectively informing the public, especially women, on nuclear energy and radiation, in particular by: meeting regularly to exchange ideas and experiences between countries' WIN information groups, establishing country WIN groups in nuclear countries as widely as practical, supporting each other across borders, working out shared information techniques and information materials for international use. WIN is open to female nuclear and radiation professionals and academics as well as communications specialists, from all over the world, pledged to adhere to the goals of this Charter. The first WINFO Quarterly Newsletter of Women in Nuclear has been published

  13. Role of the operator in nuclear power plants as determined from a survey of the North American nuclear community

    International Nuclear Information System (INIS)

    Spelt, P.F.

    1993-01-01

    Results of an empirical survey, one of the first to deal with the Role of the Operator in nuclear power plants in North America, are presented. The survey showed that the theoretical match between operators' responsibility and control (written definition of ''role'') is not supported by the numerical evaluations of these two concepts. Across a dimension from existing to advanced reactors, there is increasingly a shift from hands-on manipulation and readout-by-readout information integration by the operators to a role in which the operator is a passive monitor whose primary task is to give permissives to the automated control system. There is a decreasing degree of control for operators, while responsibility remains high. Decreased control coupled with high responsibility may create shift operating staff problems

  14. Determination of activity by gamma spectrometry of radionuclides present in drums of residues generated in nuclear centrals

    International Nuclear Information System (INIS)

    Aguiar, J.C.; Fernandez, J.

    2006-01-01

    The generation of radioactive residuals in nuclear centrals as CNA I (Atucha I Nuclear Central) and CNE (Embalse Nuclear Central) makes that the measurement of those radionuclides has been a previous stage to the waste management. A method used in those nuclear centrals it is the gamma spectrometry with HPGe detectors, previous to the immobilization of the residual in a cemented matrix, with this the contact with the external agents and its possible dispersion to the atmosphere in the short term is avoided. The ARN (Nuclear Regulatory Authority) of Argentina it carries out periodically intercomparisons and evaluations of the measurement and procedures systems used in the nuclear power stations for the correct measurement and determination of activity of radioactive residuals by gamma spectrometry. In this work an independent method of measurement is exposed to the nuclear power stations. To determine the activity of the residuals by gamma spectrometry deposited in drums, it is required of the precise knowledge of the efficiency curve for such geometry and matrix. Due to the RNA doesn't have a pattern of these characteristics, a mathematical model has been used to obtain this efficiency curve. For it, it is necessary to determine previously: 1) the geometric efficiency or solid angle sustained by the source-detector system (drum-detector) applying a mathematical model described in this work. 2) To estimate the auto-attenuation factor that present the photons in the cemented matrix, these calculations are carried out with a simple equation and its are verified with the Micro Shield 6.10 program. The container commonly used by these nuclear power stations its are drums for 220 liters constructed with SAE 1010 steel and with a thickness of 0.127 cm, with an approximate weight 7.73 Kg., internal diameter of 57.1 cm, and height: 87 cm. The results obtained until the moment register a discrepancy from 5 to 10% with relationship to the measurements carried out by the

  15. Determination of the nuclear electric charge distribution of samarium isotopes 144, 148, 150, 152, 154 by the muonic atom method

    International Nuclear Information System (INIS)

    Barreau, Pierre.

    1977-01-01

    The theory of the nucleus-negative muon system in the case of electrical interactions is discussed. The interactions of muons with the samarium isotopes 152, 154, 144, 148, 150 are investigated. After a description of the experimental device, from muon beam production to data acquisition (detection of the gamma spectra), the results are analyzed and the nuclear charge distribution parameters determined: for each isotope the absolute value of c (half-density radius) and t (skin thickness); for 152 Sm and 154 Sm the parameter β 2 (quadrupolar defomation). Nuclear polarization was accounted for throughout the analysis [fr

  16. Application of extreme value distribution function in the determination of standard meteorological parameters for nuclear power plants

    International Nuclear Information System (INIS)

    Jiang Haimei; Liu Xinjian; Qiu Lin; Li Fengju

    2014-01-01

    Based on the meteorological data from weather stations around several domestic nuclear power plants, the statistical results of extreme minimum temperatures, minimum. central pressures of tropical cyclones and some other parameters are calculated using extreme value I distribution function (EV- I), generalized extreme value distribution function (GEV) and generalized Pareto distribution function (GP), respectively. The influence of different distribution functions and parameter solution methods on the statistical results of extreme values is investigated. Results indicate that generalized extreme value function has better applicability than the other two distribution functions in the determination of standard meteorological parameters for nuclear power plants. (authors)

  17. Investigating the Role of Akt1 in Prostate Cancer Development Through Phosphorylation-Dependent Regulation of Skp2 Stability and Oncogenic Function

    Science.gov (United States)

    2010-09-01

    plausible that for large animals with a longer life span than mice, which requires more cell division events, an additional layer of cell cycle control...occurs partially through the increased tran- scriptional levels of SGK1 mRNA and partially through other layers of posttranslational regulation (Loffing et...markers ( urease !545 kDa, mouse monoclonal IgG !180 kDa, human serum albumin!68 kDa) and determining their retention times on Coomassie- stained SDS

  18. Energetics of endurance exercise in young horses determined by nuclear magnetic resonance metabolomics

    Directory of Open Access Journals (Sweden)

    Margaux Marie-Hélène, Olivia Luck

    2015-07-01

    Full Text Available Long-term endurance exercise severely affects metabolism in both human and animal athletes resulting in serious risk of metabolic disorders during or after competition. Young horses (up to 6 years old can compete in races up to 90 km despite limited scientific knowledge of energetic metabolism responses to long distance exercise in these animals. The hypothesis of this study was that there would be a strong effect of endurance exercise on the metabolomic profiles of young horses and that the energetic metabolism response in young horses would be different from that of more experienced horses. Metabolomic profiling is a powerful method that combines Nuclear magnetic resonance (NMR spectrometry with supervised orthogonal projection on latent structure (OPLS statistical analysis. 1H-NMR spectra were obtained from plasma samples drawn from young horses (before and after competition. The spectra obtained before and after the race from the same horse (92 samples were compared using OPLS. The statistical parameters showed the robustness of the model (R2Y=0.947, Q2Y=0.856 and CV-ANOVA p-value < 0.001. For confirmation of the predictive value of the model, a test set of 104 sample spectra were projected by the model, which provided perfect predictions as the area under the receiving-operator curve was 1. The metabolomic profile determined with the OPLS model showed that glycemia after the race was lower than glycemia before the race, despite the involvement of lipid and protein catabolism. An OPLS model was calculated to compare spectra obtained on plasma taken after the race from 6-year-old horses and from experienced horses (cross-validated ANOVA p-value < 0.001. The comparison of metabolomic profiles in young horses to those from experienced horses showed that experienced horses maintained their glycemia with higher levels of lactate and a decrease of plasma lipids after the race.

  19. Determination of the isotopic composition of neutron irradiated nuclear fuel materials by MCNPX

    International Nuclear Information System (INIS)

    Cerba, S.; Necas, V.

    2012-01-01

    The aim of this study was to examine whether the MCNPX code can provide acceptable results in fuel depletion calculation. There sets of cross section libraries have been process with the NJOY code on the basis of three different cross section evaluations. These libraries had been validated and the statistical evaluation of the results showed that all three sets had been processed correctly and they are applicable for the burnup calculation. To verify the burnup capabilities of the MCNPX code the third case of the IV-B phase of the OECD NEA Burnup credit benchmark has been chosen, which is a code to code validation. The main task was to compare the k and the isotope concentrations at 4 burnup steps. The comparison of the calculation results clearly showed that the results obtained by MCNPX were in the range of other codes used in nuclear research. There were some discrepancies between the calculated and the benchmark data, but it was not possible to definitely conclude whether they were caused by the accuracy of the program or not. On the one hand, the results showed that some discrepancies may have been caused by the different cross section evaluations used in the calculation. On the other hand we cannot determine, how accurate the results from the other codes were; thus the deviations that at the first glance seemed to be high might not have necessarily meant inaccuracies in the calculation. Despite the fact that the MCNPX code is still in development, we can conclude that the code is capable of obtaining relevant results. (authors)

  20. Optimization of automation: III. Development of optimization method for determining automation rate in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Seung Min; Kim, Jong Hyun; Kim, Man Cheol; Seong, Poong Hyun

    2016-01-01

    Highlights: • We propose an appropriate automation rate that enables the best human performance. • We analyze the shortest working time considering Situation Awareness Recovery (SAR). • The optimized automation rate is estimated by integrating the automation and ostracism rate estimation methods. • The process to derive the optimized automation rate is demonstrated through case studies. - Abstract: Automation has been introduced in various industries, including the nuclear field, because it is commonly believed that automation promises greater efficiency, lower workloads, and fewer operator errors through reducing operator errors and enhancing operator and system performance. However, the excessive introduction of automation has deteriorated operator performance due to the side effects of automation, which are referred to as Out-of-the-Loop (OOTL), and this is critical issue that must be resolved. Thus, in order to determine the optimal level of automation introduction that assures the best human operator performance, a quantitative method of optimizing the automation is proposed in this paper. In order to propose the optimization method for determining appropriate automation levels that enable the best human performance, the automation rate and ostracism rate, which are estimation methods that quantitatively analyze the positive and negative effects of automation, respectively, are integrated. The integration was conducted in order to derive the shortest working time through considering the concept of situation awareness recovery (SAR), which states that the automation rate with the shortest working time assures the best human performance. The process to derive the optimized automation rate is demonstrated through an emergency operation scenario-based case study. In this case study, four types of procedures are assumed through redesigning the original emergency operating procedure according to the introduced automation and ostracism levels. Using the

  1. CSNI Technical Opinion Papers No. 14 - Nuclear Licensee Organisational Structures, Resources and Competencies: Determining their Suitability

    International Nuclear Information System (INIS)

    2012-01-01

    The way in which nuclear licensees' organisations are structured and resourced clearly has a potential impact on nuclear safety. As experience has continually demonstrated, operating organisations with a strong training programme for personnel, adequate resourcing and overall effective leadership and management perform more effectively in times of crisis than those lacking in one or more of these areas. In parallel, the nuclear industry is developing new resource deployment strategies which are making increased use of contractors and leading to changes in organisational structure, which in turn create challenges for the continued safe operation of nuclear facilities. This technical opinion paper represents the consensus among human and organisational factor specialists in NEA member and associated countries on the methods, approaches and good practices to be followed in designing an organisation with a strong safety focus while meeting business needs. It also considers some of the attributes that an organisation which is effectively managing its resources and capabilities might demonstrate

  2. Proposal for the determination of nuclear masses by high-precision spectroscopy of Rydberg states

    International Nuclear Information System (INIS)

    Wundt, B J; Jentschura, U D

    2010-01-01

    The theoretical treatment of Rydberg states in one-electron ions is facilitated by the virtual absence of the nuclear-size correction, and fundamental constants like the Rydberg constant may be in the reach of planned high-precision spectroscopic experiments. The dominant nuclear effect that shifts transition energies among Rydberg states therefore is due to the nuclear mass. As a consequence, spectroscopic measurements of Rydberg transitions can be used in order to precisely deduce nuclear masses. A possible application of this approach to hydrogen and deuterium, and hydrogen-like lithium and carbon is explored in detail. In order to complete the analysis, numerical and analytic calculations of the quantum electrodynamic self-energy remainder function for states with principal quantum number n = 5, ..., 8 and with angular momentum l = n - 1 and l = n - 2 are described (j = l +- 1/2).

  3. Proposal for the determination of nuclear masses by high-precision spectroscopy of Rydberg states

    Energy Technology Data Exchange (ETDEWEB)

    Wundt, B J; Jentschura, U D [Department of Physics, Missouri University of Science and Technology, Rolla, MO 65409-0640 (United States)

    2010-06-14

    The theoretical treatment of Rydberg states in one-electron ions is facilitated by the virtual absence of the nuclear-size correction, and fundamental constants like the Rydberg constant may be in the reach of planned high-precision spectroscopic experiments. The dominant nuclear effect that shifts transition energies among Rydberg states therefore is due to the nuclear mass. As a consequence, spectroscopic measurements of Rydberg transitions can be used in order to precisely deduce nuclear masses. A possible application of this approach to hydrogen and deuterium, and hydrogen-like lithium and carbon is explored in detail. In order to complete the analysis, numerical and analytic calculations of the quantum electrodynamic self-energy remainder function for states with principal quantum number n = 5, ..., 8 and with angular momentum l = n - 1 and l = n - 2 are described (j = l {+-} 1/2).

  4. Experimental determination of fuel surface temperature in the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Khang, Ngo Phu; Huy, Ngo Quang; An, Tran Khac; Lam, Pham Van [Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    Measured fuel surface temperatures, obtained at various locations of the core of the Dalat Nuclear Research Reactor under normal operating conditions, are presented, and some thermal characteristics of the reactor are discussed. (author). 2 refs., 11 figs., 2 tabs.

  5. The four and a half LIM domains 2 (FHL2) regulates ovarian granulosa cell tumor progression via controlling AKT1 transcription

    OpenAIRE

    Hua, G; He, C; Lv, X; Fan, L; Wang, C; Remmenga, S W; Rodabaugh, K J; Yang, L; Lele, S M; Yang, P; Karpf, A R; Davis, J S; Wang, C

    2016-01-01

    The four and a half LIM domains 2 (FHL2) has been shown to play important roles in the regulation of cell proliferation, survival, adhesion, motility and signal transduction in a cell type and tissue-dependent manner. However, the function of FHL2 in ovarian physiology and pathology is unclear. The aim of this study was to determine the role and functional mechanism of FHL2 in the progression of ovarian granulosa cell tumors (GCTs). Immunohistochemical analysis indicated that FHL2 was overexp...

  6. Determination of chemical forms of C-14 in liquid discharges from nuclear power plants

    Czech Academy of Sciences Publication Activity Database

    Světlík, Ivo; Fejgl, M.; Povinec, P. P.; Kořínková, Tereza; Tomášková, Lenka; Pospíchal, J.; Kurfiřt, M.; Striegler, R.; Kaufmanová, M.

    2017-01-01

    Roč. 177, OCT (2017), s. 256-260 ISSN 0265-931X Institutional support: RVO:61389005 Keywords : analytical routines * dissolved organic forms of C-14 (DIC) * dissolved inorganic forms of C-14 (DOC) * Nuclear power plant (NPP) * liquid releases Subject RIV: DL - Nuclear Waste, Radioactive Pollution ; Quality OBOR OECD: Environment al sciences (social aspects to be 5.7) Impact factor: 2.310, year: 2016

  7. Careful determination of inservice inspection of piping by computer analysis in nuclear power plant

    International Nuclear Information System (INIS)

    Lim, H. T.; Lee, S. L.; Lee, J. P.; Kim, B. C.

    1992-01-01

    Stress analysis has been performed using computer program ANSYS in the pressurizer surge line in order to predict possibility of crack generation due to thermal stratification phenomena in pipes connected to reactor coolant system of Nuclear power plants. Highly vulnerable area to crack generation has been chosen by the analysis of fatigue due to thermal stress in pressurizer surge line. This kind of result can be helpful to choose the location requiring intensive care during inservice inspection of nuclear power plants.

  8. Technosocial Modeling for Determining the Status and Nature of a State’s Nuclear Activities

    Energy Technology Data Exchange (ETDEWEB)

    Gastelum, Zoe N.; Harvey, Julia B.

    2009-09-25

    The International Atomic Energy Agency State Evaluation Process: The Role of Information Analysis in Reaching Safeguards Conclusions (Mathews et al. 2008), several examples of nonproliferation models using analytical software were developed that may assist the IAEA with collecting, visualizing, analyzing, and reporting information in support of the State Evaluation Process. This paper focuses on one of the examples a set of models developed in the Proactive Scenario Production, Evidence Collection, and Testing (ProSPECT) software that evaluates the status and nature of a state’s nuclear activities. The models use three distinct subject areas to perform this assessment: the presence of nuclear activities, the consistency of those nuclear activities with national nuclear energy goals, and the geopolitical context in which those nuclear activities are taking place. As a proof-of-concept for the models, a crude case study was performed. The study, which attempted to evaluate the nuclear activities taking place in Syria prior to September 2007, yielded illustrative, yet inconclusive, results. Due to the inconclusive nature of the case study results, changes that may improve the model’s efficiency and accuracy are proposed.

  9. Quantifying the passive gamma signal from spent nuclear fuel in support of determining the plutonium content in spent nuclear fuel with nondestructive assay

    Energy Technology Data Exchange (ETDEWEB)

    Fensin, Michael L [Los Alamos National Laboratory; Tobin, Steven J [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory

    2009-01-01

    The objective of safeguarding nuclear material is to deter diversions of significant quantities of nuclear materials by timely monitoring and detection. There are a variety of motivations for quantifying plutonium in spent fuel (SF), by means of nondestructive assay (NDA), in order to meet this goal. These motivations include the following: strengthening the capabilities of the International Atomic Energy Agencies ability to safeguard nuclear facilities, shipper/receiver difference, input accountability at reprocessing facilities and burnup credit at repositories. Many NDA techniques exist for measuring signatures from SF; however, no single NDA technique can, in isolation, quantify elemental plutonium in SF. A study has been undertaken to determine the best integrated combination of 13 NDA techniques for characterizing Pu mass in spent fuel. This paper focuses on the development of a passive gamma measurement system in support the spent fuel assay system. Gamma ray detection for fresh nuclear fuel focuses on gamma ray emissions that directly coincide with the actinides of interest to the assay. For example, the 186-keV gamma ray is generally used for {sup 235}U assay and the 384-keV complex is generally used for assaying plutonium. In spent nuclear fuel, these signatures cannot be detected as the Compton continuum created from the fission products dominates the signal in this energy range. For SF, the measured gamma signatures from key fission products ({sup 134}Cs, {sup 137}Cs, {sup 154}Eu) are used to ascertain burnup, cooling time, and fissile content information. In this paper the Monte Carlo modeling set-up for a passive gamma spent fuel assay system will be described. The set-up of the system includes a germanium detector and an ion chamber and will be used to gain passive gamma information that will be integrated into a system for determining Pu in SF. The passive gamma signal will be determined from a library of {approx} 100 assemblies that have been

  10. Modeling and Simulation Monte Carlo by the MCNP code for determining neutron parameters of the nuclear reactor-subcritical assembly in CNSTN

    International Nuclear Information System (INIS)

    Romdhani, Ibtissem

    2014-01-01

    As part of developing its nuclear infrastructure base, the National Science and Technology Center Nuclear (CNSTN) examines the technical feasibility of setting up a new installation of subcritical assembly. Our study focuses on determining the neutron parameters of a nuclear zero power reactor based on Monte Carlo simulation MCNP. The objective of the simulation is to model the installation, determine the effective multiplication factor, and spatial distribution of neutron flux.

  11. Notification determining technical details concerning measures for transportation of nuclear fuel materials

    International Nuclear Information System (INIS)

    1977-01-01

    These provisions are established on the basis of and to enforce ''The regulation for installation and operation of reactor'', ''The regulation concerning the fabricating business of nuclear fuel'' and ''The regulations concerning the reprocessing business of spent fuel''. The terms used hereinafter are according to those used in such regulations. The limit of radioactivity concentration of things contaminated by the nuclear fuel materials which are not required to be enclosed in vessels is defined in the lists attached. In the applications for the approval of the measures concerning the transport of things remarkably difficult to be enclosed in vessels, the name and the address of the applicant, the kind, quantity, form and constitution of the thing contaminated by the nuclear fuel materials to be transported, the date and route of the transport and the measures for the prevention of injuries during the transport must be written. The limit of quantity of nuclear fuel materials classifying the performance of vessels is defined respectively in the lists attached. The radiation dose rates provided for by the Director General of the Science and Technology Agency concerning transported things and transporting apparatuses are 200 millirem per hour on the surfaces of such things and containers. The nuclear fission materials specified, for which the measures for the prevention of criticality are especially required, include uranium 233, uranium 235, plutonium 238, plutonium 239, plutonium 241, and the chemical compounds of such substances, and the nuclear fuel materials containing one or two and more of such substances, excluding the nuclear fuel materials with less than 15 grams of such uranium and plutonium. (Okada, K.)

  12. Determination of technical details concerning measures for transportation of nuclear fuel materials in the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The determination is defined under the regulations concerning the fabricating business of nuclear fuel materials, the regulation concerning installation and operation of test reactor, the regulations concerning the reprocessing business of spent fuel and the regulations concerning the uses of nuclear source materials. The notification determining technical details concerning measures for transportation of nuclear fuel materials is abolished. Measures for prevention of hazard designated by the Director General of Science and Technology Agency include such ones not to let radioactive materials easily fly about or leak in regular transport, not to let rain water easily penetrate or make each exterior side of a cubic load more than 10 centi-meters. The application for permission shall be filed for transportation of things highly difficult to be sealed in a vessel, listing name and address of the applicant, kind, quantity, form and nature of the load contaminated by nuclear fuel materials, date and route of transfer and measures taken for prevention of hazard in transport. Radiation doses of load and transporting apparatus are stipulated by the Director for an hour as 200 mili-rem on the surface of load, 10 mili-rem at the distance of 1 meter from the surface of load, and 200 mili-rem on the surface of the vehicle, etc. Dangerous things, signals and radiation dose of particular loads are specified respectively. (Okada, K.)

  13. Prospects for an energy determination of the {sup 229m}Th nuclear isomer via IC electrons

    Energy Technology Data Exchange (ETDEWEB)

    Seiferle, B.; Wense, L. v.d.; Thirolf, P.G. [LMU Muenchen, Garching (Germany); Laatiaoui, M. [GSI, Darmstadt (Germany); Helmholtz Institut Mainz, Mainz (Germany)

    2016-07-01

    Of all known nuclear excited states, the isomeric first excited state of {sup 229}Th possesses the lowest excitation energy reported to be E{sup *}=7.6(5) eV (=163(11) nm). This opens up the possibility to drive the transition with a laser and makes {sup 229m}Th an interesting candidate for future developments linking nuclear and atomic physics, such as a nuclear optical clock or a nuclear γ-ray laser. Still, for a direct laser excitation, the knowledge on the energy and half-life of the isomer is not precise enough. In this work and for the expected transition energy, neutral {sup 229}Th decays via the emission internal conversion (IC) electrons with an energy of 1.2 eV (i.e. difference between E* and the 1{sup st} ionization potential). A {sup 233}U α-recoil source is placed in a buffer-gas stopping cell. {sup 229}Th ions, of which 2% are in the isomeric state are recoiled out of the source. RF- and DC electrode structures form an ion beam out of all the recoil ions. Afterwards, {sup 229(m)}Th ions are separated from other short-lived daughter isotopes with a quadrupole mass separator and can be prepared for further experiments. The poster gives prospects for an energy determination of the IC electrons emitted during the decay of the isomer and for a corresponding half-life determination with this experimental setup.

  14. Reactivity determination in accelerator driven nuclear reactors by statistics from neutron detectors (Feynman-Alpha Method)

    International Nuclear Information System (INIS)

    Ceder, M.

    2002-03-01

    The Feynman-alpha method is used in traditional nuclear reactors to determine the subcritical reactivity of a system. The method is based on the measurement of the mean number and the variance of detector counts for different measurement times. The measurement is performed while a steady-state neutron flux is maintained in the reactor by an external neutron source, as a rule a radioactive source. From a plot of the variance-to-mean ratio as a function of measurement time ('gate length'), the reactivity can be determined by fitting the measured curve to the analytical solution. A new situation arises in the planned accelerator driven systems (ADS). An ADS will be run in a subcritical mode, and the steady flux will be maintained by an accelerator based source. Such a source has statistical properties that are different from those of a steady radioactive source. As one example, in a currently running European Community project for ADS research, the MUSE project, the source will be a periodically pulsed neutron generator. The theory of Feynman-alpha method needs to be extended to such nonstationary sources. There are two ways of performing and evaluating such pulsed source experiments. One is to synchronise the detector time gate start with the beginning of an incoming pulse. The Feynman-alpha method has been elaborated for such a case recently. The other method can be called stochastic pulsing. It means that there is no synchronisation between the detector time gate start and the source pulsing, i.e. the start of each measurement is chosen at a random time. The analytical solution to the Feynman-alpha formula from this latter method is the subject of this report. We have obtained an analytical Feynman-alpha formula for the case of stochastic pulsing by two different methods. One is completely based on the use of the symbolic algebra code Mathematica, whereas the other is based on complex function techniques. Closed form solutions could be obtained by both methods

  15. Reactivity determination in accelerator driven nuclear reactors by statistics from neutron detectors (Feynman-Alpha Method)

    Energy Technology Data Exchange (ETDEWEB)

    Ceder, M

    2002-03-01

    The Feynman-alpha method is used in traditional nuclear reactors to determine the subcritical reactivity of a system. The method is based on the measurement of the mean number and the variance of detector counts for different measurement times. The measurement is performed while a steady-state neutron flux is maintained in the reactor by an external neutron source, as a rule a radioactive source. From a plot of the variance-to-mean ratio as a function of measurement time ('gate length'), the reactivity can be determined by fitting the measured curve to the analytical solution. A new situation arises in the planned accelerator driven systems (ADS). An ADS will be run in a subcritical mode, and the steady flux will be maintained by an accelerator based source. Such a source has statistical properties that are different from those of a steady radioactive source. As one example, in a currently running European Community project for ADS research, the MUSE project, the source will be a periodically pulsed neutron generator. The theory of Feynman-alpha method needs to be extended to such nonstationary sources. There are two ways of performing and evaluating such pulsed source experiments. One is to synchronise the detector time gate start with the beginning of an incoming pulse. The Feynman-alpha method has been elaborated for such a case recently. The other method can be called stochastic pulsing. It means that there is no synchronisation between the detector time gate start and the source pulsing, i.e. the start of each measurement is chosen at a random time. The analytical solution to the Feynman-alpha formula from this latter method is the subject of this report. We have obtained an analytical Feynman-alpha formula for the case of stochastic pulsing by two different methods. One is completely based on the use of the symbolic algebra code Mathematica, whereas the other is based on complex function techniques. Closed form solutions could be obtained by both methods

  16. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  17. Cell Cycle Regulates Nuclear Stability of AID and Determines the Cellular Response to AID.

    Directory of Open Access Journals (Sweden)

    Quy Le

    2015-09-01

    Full Text Available AID (Activation Induced Deaminase deaminates cytosines in DNA to initiate immunoglobulin gene diversification and to reprogram CpG methylation in early development. AID is potentially highly mutagenic, and it causes genomic instability evident as translocations in B cell malignancies. Here we show that AID is cell cycle regulated. By high content screening microscopy, we demonstrate that AID undergoes nuclear degradation more slowly in G1 phase than in S or G2-M phase, and that mutations that affect regulatory phosphorylation or catalytic activity can alter AID stability and abundance. We directly test the role of cell cycle regulation by fusing AID to tags that destabilize nuclear protein outside of G1 or S-G2/M phases. We show that enforced nuclear localization of AID in G1 phase accelerates somatic hypermutation and class switch recombination, and is well-tolerated; while nuclear AID compromises viability in S-G2/M phase cells. We identify AID derivatives that accelerate somatic hypermutation with minimal impact on viability, which will be useful tools for engineering genes and proteins by iterative mutagenesis and selection. Our results further suggest that use of cell cycle tags to regulate nuclear stability may be generally applicable to studying DNA repair and to engineering the genome.

  18. Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2002-05-01

    The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately

  19. Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately.

  20. Simple and rapid determination methods for low-level radioactive wastes generated from nuclear research facilities. Guidelines for determination of radioactive waste samples

    International Nuclear Information System (INIS)

    Kameo, Yutaka; Shimada, Asako; Ishimori, Ken-ichiro; Haraga, Tomoko; Katayama, Atsushi; Nakashima, Mikio; Hoshi, Akiko

    2009-10-01

    Analytical methods were developed for simple and rapid determination of U, Th, and several nuclides, which are selected as important nuclides for safety assessment of disposal of wastes generated from research facilities at Nuclear Science Research Institute and Oarai Research and Development Center. The present analytical methods were assumed to apply to solidified products made from miscellaneous wastes by plasma melting in the Advanced Volume Reduction Facilities. In order to establish a system to analyze the important nuclides in the solidified products at low cost and routinely, we have advanced the development of a high-efficiency non-destructive measurement technique for γ-ray emitting nuclides, simple and rapid methods for pretreatment of solidified product samples and subsequent radiochemical separations, and rapid determination methods for long-lived nuclides. In the present paper, we summarized the methods developed as guidelines for determination of radionuclides in the low-level solidified products. (author)

  1. Constitutional determinants of nuclear power plant upgrading; Verfassungsrechtliche Determinanten bei der Nachruestung von Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Mann, Thomas [Goettingen Univ. (Germany). Lehrstuhl fuer Oeffentliches Recht, insbesondere Verwaltungsrecht; NdsOVG - Niedersaechsisches Oberverwaltungsgericht (Germany)

    2013-11-01

    Around half a year ago the European stress test for nuclear power plants, a precautionary measure initiated by the European Council in March 2011 in response to the Fukushima disaster, revealed that while German nuclear power plants show a high degree of robustness compared with those in other European countries, they nevertheless required upgrading in one or the other respect (earthquake warning systems, protection against crashing civil passenger airplanes). The present article investigates whether this upgrading requirement can justify an injunction to carry out structural retrofitting measures or whether obligations to this end can be excluded on grounds of reasonability in view of the recent decision taken by the German parliament to phase out nuclear energy.

  2. Construction of an experimental simplified model for determining of flow parameters in chemical reactors, using nuclear techniques

    International Nuclear Information System (INIS)

    Araujo Paiva, J.A. de.

    1981-03-01

    The development of a simplified experimental model for investigation of nuclear techniques to determine the solid phase parameters in gas-solid flows is presented. A method for the measurement of the solid phase residence time inside a chemical reactor of the type utilised in the cracking process of catalytic fluids is described. An appropriate radioactive labelling technique of the solid phase and the construction of an eletronic timing circuit were the principal stages in the definition of measurement technique. (Author) [pt

  3. Air temperature determination inside residual heat removal pump room of Angra-1 nuclear power plant after a design basic accident

    International Nuclear Information System (INIS)

    Siniscalchi, Marcio Rezende

    2005-01-01

    This work develops heat transfer theoretical models for determination of air temperature inside the Residual Heat Removal Pump Room of Angra 1 Nuclear Power Plant after a Design Basis Accident without forced ventilation. Two models had been developed. The differential equations are solved by analytical methods. A software in FORTRAN language are developed for simulations of temperature inside rooms for different geometries and materials. (author)

  4. Total gamma activity measurements for determining the radioactivity of residual materials from nuclear power stations

    International Nuclear Information System (INIS)

    Auler, I.; Meyer, M.; Stickelmann, J.

    1995-01-01

    Large amounts of residual materials from retrofitting measures and from decommissioning of nuclear power stations shows such a weak level of radioactivity that they could be released after decision measurements. Expenses incurred with complex geometry cannot be taken with common methods. NIS developed a Release Measurement Facility (RMF) based on total gamma activity measurements especially for these kind of residual materials. The RMF has been applied for decision measurements in different nuclear power plants. Altogether about 2,000 Mg of various types of materials have been measured up to now. More than 90 % of these materials could be released 0 without any restriction after decision measurements

  5. Careful Determination of Inservice Inspection of piping by Computer Analysis in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lim, H. T.; Lee, S. L.; Lee, J. P.; Kim, B. C.

    1992-01-01

    Stress analysis has been performed using computer program ANSYS in the pressurizer surge line in accordance with ASME Sec. III in order to predict possibility of fatigue failure due to thermal stratification phenomena in pipes connected to reactor coolant system of nuclear power plants. Highly vulnerable area to crack generation has been chosen by the analysis of fatigue due to thermal stress in pressurizer surge line. This kind of result can be helpful to choose the location requiring intensive care during inservice inspection of nuclear power plants

  6. Determination of the neutron flux for the Yankee Rowe experiment in the Ford Nuclear Reactor

    International Nuclear Information System (INIS)

    Cacciapouti, R.J.; Petrusha, L.

    1994-01-01

    Yankee Atomic Electric Company undertook a Test Irradiation Program at the Ford Nuclear Reactor of the University of Michigan. The program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials. The program was also intended to remove uncertainties in the existing reactor vessel fluence and damage predictions on the Yankee Rowe reactor vessel steel. Since this is the first in-core experiment of this type for the Ford Nuclear Reactor, the measurement of the reaction rate and the estimate of the fluence are presented

  7. Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 2: Data standardization for tank calibration

    International Nuclear Information System (INIS)

    2007-01-01

    Measurements of the volume and height of liquid in a process accountancy tank are often made in order to estimate or verify the tank's calibration or volume measurement equation. The calibration equation relates the response of the tank's measurement system to some independent measure of tank volume. The ultimate purpose of the calibration exercise is to estimate the tank's volume measurement equation (the inverse of the calibration equation), which relates tank volume to measurement system response. In this part of ISO 18213, it is assumed that the primary measurement-system response variable is liquid height and that the primary measure of liquid content is volume. This part of ISO 18213 presents procedures for standardizing a set of calibration data to a fixed set of reference conditions so as to minimize the effect of variations in ambient conditions that occur during the measurement process. The procedures presented herein apply generally to measurements of liquid height and volume obtained for the purpose of calibrating a tank (i.e. calibrating a tank's measurement system). When used in connection with other parts of ISO 18213, these procedures apply specifically to tanks equipped with bubbler probe systems for measuring liquid content. The standardization algorithms presented herein can be profitably applied when only estimates of ambient conditions, such as temperature, are available. However, the most reliable results are obtained when relevant ambient conditions are measured for each measurement of volume and liquid height in a set of calibration data. Information is provided on scope, physical principles, data required, calibration data, dimensional changes in the tank, multiple calibration runs and results on standardized calibration data. Four annexes inform about density of water, buoyancy corrections for mass determination, determination of tank heel volume and statistical method for aligning data from several calibration runs. A bibliography is

  8. Deterministic and probabilistic approach to determine seismic risk of nuclear power plants; a practical example

    International Nuclear Information System (INIS)

    Soriano Pena, A.; Lopez Arroyo, A.; Roesset, J.M.

    1976-01-01

    The probabilistic and deterministic approaches for calculating the seismic risk of nuclear power plants are both applied to a particular case in Southern Spain. The results obtained by both methods, when varying the input data, are presented and some conclusions drawn in relation to the applicability of the methods, their reliability and their sensitivity to change

  9. Accuracy determination of dose calibrators in Nuclear Medicine Centers using Tl-201

    International Nuclear Information System (INIS)

    Sattari, A.; Feizi, H.; Ghafoori, M.

    2008-01-01

    Full text: Correct administrated activity of radiopharmaceuticals is an important factor to ensure that administrated radiopharmaceutical is accurately measured and to avoid unnecessary exposure to patients. In this article, nuclear medicine group and Secondary Standard Dosimetry Laboratory (SSDL), has introduced a comparison study with 201 Tl to check the accuracy of dose calibrators in some nuclear medicine centers. First, the dose calibrator in cyclotron department was calibrated by SSDL using 133 Ba, 57 Co, 137 Cs and standard Europium sources. Then, 2ml produced 201 Tl solution containing 16±0.1 mCi was accurately sub-divided into a series of 10 ml Schott vials and delivered to 12 nuclear medicine centers that have been participated in this study. Participants were requested to assay their Schott vials in their dose calibrators at the same time and report the result on the especial sheet. Difference between the activities values reported by participants (A p ) with assayed activity on cyclotron department (Ac), defined as error value. In comparison of A c with A p , 10 centers (83%) has positive and 2 others (17%) has negative error. The range of positive error 2.6% -17.9% and range of negative error 5%-8.5%, by the average of 8.67 and %SD = 7.39 have been calculated. In conclusion, although nuclear medicine centers do calibration on their dose calibrators but establishment a regular audit system seems to be necessary. (author)

  10. Nuclear DNA content of the hybrid plant pathogen Phytophthora andina determined by flow cytometry.

    Science.gov (United States)

    Wang, Jianan; Presser, Jackson W; Goss, Erica M

    2016-09-01

    Phytophthora andina is a heterothallic plant pathogen of Andean solanaceous hosts and is an interspecific hybrid of P. infestans and an unknown Phytophthora species. The objective of this study was to estimate the nuclear DNA content of isolates in three clonal lineages of P. andina relative to P. infestans Twelve isolates of P. andina and six isolates of P. infestans were measured for nuclear DNA content by propidium iodide-stained flow cytometry. We found that the DNA content of P. andina was similar but slightly smaller, on average, than that of our sample of P. infestans isolates. This is consistent with P. andina being a homoploid hybrid rather than allopolyploid hybrid. Nuclear DNA content was more variable among a smaller sample of P. infestans isolates, including a putative triploid isolate from Mexico, but small differences in nuclear DNA content were also observed among P. andina isolates. Both species appear to be able to tolerate significant variation in genome size. © 2016 by The Mycological Society of America.

  11. Determination of Ploidy Level and Nuclear DNA Content in the Droseraceae by Flow Cytometry

    Czech Academy of Sciences Publication Activity Database

    Hoshi, Y.; Azumatani, M.; Suyama, T.; Adamec, Lubomír

    2017-01-01

    Roč. 82, č. 3 (2017), s. 321-327 ISSN 0011-4545 Institutional support: RVO:67985939 Keywords : nuclear DNA content * genome size * Droseraceae Subject RIV: EB - Genetics ; Molecular Biology OBOR OECD: Plant sciences, botany Impact factor: 0.913, year: 2016

  12. Experimental methods for burn-up determination in nuclear fuels, 1

    International Nuclear Information System (INIS)

    Taddei, J.F. de A.C.; Rodrigues, C.

    1977-01-01

    A method is presented that allows the calculation of the total percentage of atoms having undergone fission ('burn up') in nuclear fuels, from the measurement of absolute amounts of fission product neodymium-148 and of uranium and plutoniun present in the spent fuel, the fission yield of neodymium-148 being known. These measurements are performed through the mass spectrometry- isotope dilution technique [pt

  13. Chemical analytical considerations on the determination of burnup in irradiated nuclear fuels

    International Nuclear Information System (INIS)

    Cretella, R.F.; Servant, R.E.

    1989-01-01

    Burnup in an irradiated nuclear fuel may be defined as the energy produced per mass unit, from the time the fuel is introduced into the reactor and until a given moment. It is usually shown in megawatt/day or megawatt/hour generated per ton or kilo of fuel. It is also indicated as the number of fission produced per volume unit (cm 3 ) or per every 100 initial fissionable atoms. The yield of a power plant is directly related to the burnup of its fuel load and knowing the latter contributes to optimizing the economy in reactor operation and the related technologies. The development of nuclear fuels and the operation of reactors require doing with exact and accurate methods allowing to know the burnup. Errors in this measurement have an incidence upon the fuel design, the physical and nuclear calculations, the shielding requirements, the design of vehicles for the transportation of irradiated fuels, the engineering of processing plants, etc. All these factors, in turn, have an incidence upon the cost of nuclear power generation. (Author) [es

  14. High-accuracy fluence determination in ion beams using fluorescent nuclear track detectors

    DEFF Research Database (Denmark)

    Osinga, J.-M.; Akselrod, M.S.; Herrmann, Rochus

    2013-01-01

    We present an approach to use Al2O3:C,Mg-based fluorescent nuclear track detectors (FNTDs) and confocal laser scanning microscopy as a semiautomatic tool for fluence measurements in clinical ion beams. The method was found to cover a linear energy transfer (LET) range from at least L∞(Al2O3) = 0...

  15. Nitrogen determination in wheat by neutron activation analysis using fast neutron flux from a thermal nuclear reactor

    International Nuclear Information System (INIS)

    Ramirez G, T.

    1976-01-01

    This is a study of the technique for the determination of nitrogen and other elements in wheat flour through activation analysis with fast neutrons from a thermal nuclear reactor. The study begins with an introduction about the basis of the analytical methods, the equipment used in activation analysis and a brief description of the neutrons source. In the study are included the experiments carried out in order to determine the flux form in the site of irradiation, the N-13 half life and the interference due to the sample composition. (author)

  16. Determination of boron in aqueous solutions by solid state nuclear track detectors technique, using a filtered neutron beam

    International Nuclear Information System (INIS)

    Moraes, M.A.P.V. de; Pugliesi, R.; Khouri, M.T.F.C.

    1985-11-01

    The solid state nuclear track detectors technique has been used for determination of boron in aqueous solutions, using a filtered neutron beam. The particles tracks from the 10 B(n,α)Li 7 reaction were registered in the CR-39 film, chemically etched in a (30%) KOH solution 70 0 C during 90 minutes. The obtained results showed the usefulness of this technique for boron determination in the ppm range. The inferior detectable limit was 9 ppm. The combined track registration efficiency factor K has been evaluated in the solutions, for the CR-39 detector and its values is K= (4,60 - + 0,06). 10 -4 cm. (Author) [pt

  17. Determination of atmospheric dispersion factors in emergency situations in Almirante Alvaro Alberto nuclear power plant - unit 1

    International Nuclear Information System (INIS)

    Leao, I.L.B.

    1987-08-01

    The necessity of Knowing the atmospheric dispersion factor, used to obtain the first estimation dose in the public case for accidents with releasing of radioactive material to atmosphere in Almirante Alvaro Alberto nuclear power plant - unit I, lead to the development of a fast and efficient method to determine the dilution factors, in a pre-determined distance from the source, to be used in the dose estimate. The ACID computer program for pocket calculation allow to obtain the meteorological information to evaluate the dose. In this work the mathemathical models used and the program developed are described. (Author) [pt

  18. Determination of the characteristic limits and responses of nuclear track detectors in mixed radon and thoron atmospheres

    International Nuclear Information System (INIS)

    Röttger, Annette; Honig, Anja; Schrammel, Dieter; Strauss, Heinrich F.

    2016-01-01

    Closed nuclear track detectors are widely used for the determination of Rn-222 exposures. There are also partial open systems available, which are specially designed for the determination of the exposure to Rn-220, which is a relevant exposure in special workplaces or in specific regions of the world. This paper presents data and a detail analysis of how to determine the cross-correlation by calibration in pure Rn-222 and pure Rn-220 atm. By these means calibration coefficients for the analysis of real mixed atmospheres can be obtained. The respective decision threshold, detection limit and limits of the confidence interval were determined according to ISO 11929 (ISO 11929:2010, 2010). The exposure of detectors was performed at the radon reference chamber and the thoron progeny chamber of the Physikalisch-Technische Bundesanstalt (PTB). The analysis of track response was done at Parc RGM, while the analytical routines were developed in the Leibniz University Hanover, Institute Radioökologie und Strahlenschutz IRS at the working Group AK SIGMA (Arbeitskreis Nachweisgrenzen). - Highlights: • Analysis of exposure in reference atmospheres according ISO 11929. • Calibration of nuclear track detectors for 222 Rn and 220 Rn. • Calculation of cross-correlation by calibration in pure 222 Rn and 220 Rn atmospheres. • Thoron activity concentration should not be omitted in radon exposure determinations.

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

    Science.gov (United States)

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

    2007-09-01

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

  20. AKT3 controls mitochondrial biogenesis and autophagy via regulation of the major nuclear export protein CRM-1.

    Science.gov (United States)

    Corum, Daniel G; Tsichlis, Philip N; Muise-Helmericks, Robin C

    2014-01-01

    Our previous work has shown that Akt3 is required for mitochondrial biogenesis in primary human endothelial cells (ECs) and in Akt3-null mice; Akt3 affects subcellular localization of peroxisome proliferator-activated receptor γ coactivator-1 (PGC-1α), the master regulator of mitochondrial biogenesis. The purpose of this study is to determine the mechanism by which Akt3 controls the subcellular distribution of PGC-1α and to explore the effect on mitochondrial biogenesis and turnover during angiogenesis. Here we use standard biochemical analyses and Akt3-knockdown strategies to show that Akt3 controls the stabilization of chromosome maintenance region-1 (CRM-1), the major nuclear export receptor. Site-directed mutagenesis and association analyses show that PGC-1α nuclear export is CRM-1 dependent. Akt3 knockdown and CRM-1 overexpression cause 3-fold reductions in PGC-1α target gene expression, compared to control levels. Akt3 inhibition causes autophagy, as measured by autophagosome formation, in a CRM-1-dependent, Akt1/mTOR-independent pathway. In vivo, Akt3-null and heterozygous mice show dose-dependent decreases in angiogenesis compared to wild-type littermates (~5- and 2.5-fold decreases, respectively), as assessed by Matrigel plug assays. This correlates with an ~1.5-fold decrease in mitochondrial Cox IV expression. Our studies suggest that Akt3 is a regulator of mitochondrial dynamics in the vasculature via regulation of CRM-1-dependent nuclear export.

  1. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle; Determinacion de Uranio en Muestras Procedentes del Desmantelamiento de Instalaciones de la Primera Parte del Cielo del Combustible Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, A; Correa, E; Navarro, N; Sancho, C [Ciemat, Madrid (Spain); Angeles, A

    2000-07-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  2. Comparative analysis to determine asphalt density and content, using nuclear and traditional methods

    International Nuclear Information System (INIS)

    Margffoy S, F.R.; Robayo S, A.M.

    1989-01-01

    Quality control for flex pavement construction in Colombia for asphaltic mix, as well as for granular and granular sub base layers is made by means of methods that does not guarantee the quality of the job, due to the difficult execution of tests, which impede more to be done or due to inherent problems of the test process. Thanks to the inherent characteristics and advantages of nuclear techniques, those become the optimal alternative to this quality control job. The present research project has been developed with the objective of justifying the use of new technologies applied to road construction; making a comparative analysis between traditional methods used in our country and nuclear techniques that have been using in United States with great success in quality control in road construction

  3. Determination of the nuclear induced electrical conductivity of 3He for magnetohydrodynamic energy conversion

    International Nuclear Information System (INIS)

    Bitteker, L.; Scheuer, J.; Howe, S.

    1996-01-01

    This is the final report for a one-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The continual need for more efficient, high-output energy conversion techniques has renewed interest in nuclear-driven magnetohydrodynamic (MHD) energy conversion. To provide the fundamental knowledge required to evaluate the potential value of this concept, a one-year project aimed at measuring the nuclear-induced electrical conductivity of a 3 He/ 4 He gas mixture under thermodynamic conditions consistent with the MHD flow conditions was carried out. The range of bulk gas conditions to be considered were: pressure = 0.1 to 3800 Torr and temperature = 300 to 1500 K. The maximum neutron flux to be considered was 10 16 /cm 2 sec. The range of parameters considered surpassed previous experiments in all aspects

  4. Determining Nuclear Fingerprints: Glove Boxes, Radiation Protection, and the International Atomic Energy Agency.

    Science.gov (United States)

    Rentetzi, Maria

    2017-06-01

    In a nuclear laboratory, a glove box is a windowed, sealed container equipped with two flexible gloves that allow the user to manipulate nuclear materials from the outside in an ostensibly safe environment. As a routine laboratory device, it invites neglect from historians and storytellers of science. Yet, since especially the Gulf War, glove boxes have put the interdependence of science, diplomacy, and politics into clear relief. Standing at the intersection of history of science and international history, technological materials and devices such as the glove box can provide penetrating insight into the role of international diplomatic organizations to the global circulation and control of scientific knowledge. The focus here is on the International Atomic Energy Agency. Copyright © 2017 The Author. Published by Elsevier Ltd.. All rights reserved.

  5. Numerical determination of lateral loss coefficients for subchannel analysis in nuclear fuel bundles

    Energy Technology Data Exchange (ETDEWEB)

    Sin Kim; Goon-Cherl Park [Seoul National Univ., Seoul (Korea, Republic of)

    1995-09-01

    An accurate prediction of cross-flow based on detailed knowledge of the velocity field in subchannels of a nuclear fuel assembly is of importance in nuclear fuel performance analysis. In this study, the low-Reynolds number {kappa}-{epsilon} turbulence model has been adopted in two adjacent subchannels with cross-flow. The secondary flow is estimated accurately by the anisotropic algebraic Reynolds stress model. This model was numerically calculated by the finite element method and has been verified successfully through comparison with existing experimental data. Finally, with the numerical analysis of the velocity field in such subchannel domain, an analytical correlation of the lateral loss coefficient is obtained to predict the cross-flow rate in subchannel analysis codes. The correlation is expressed as a function of the ratio of the lateral flow velocity to the donor subchannel axial velocity, recipient channel Reynolds number and pitch-to-diameter.

  6. Understanding the determinants of electricity prices and the impact of the German Nuclear Moratorium in 2011

    International Nuclear Information System (INIS)

    Thoenes, Stefan

    2011-01-01

    This paper shows how the effect of fuel prices varies with the level of electricity demand. It analyzes the relationship between daily prices of electricity, natural gas and carbon emission allowances with a vector error correction model and a semiparametric varying smooth coefficient model. The results indicate that the electricity price adapts to fuel price changes in a long-term cointegration relationship. Different electricity generation technologies have distinct fuel price dependencies, which allows estimating the structure of the power plant portfolio by exploiting market prices. The semiparametric model indicates a technology switch from coal to gas at roughly 85% of maximum demand. It is used to analyze the market impact of the nuclear moratorium by the German Government in March 2011. Futures prices show that the market efficiently accounts for the suspended capacity and expects that several nuclear plants will not be switched on after the moratorium.

  7. A new method for determining the uranium and thorium distribution in volcanic rock samples using solid state nuclear track detectors

    International Nuclear Information System (INIS)

    Misdaq, M.A.; Bakhchi, A.; Ktata, A.; Koutit, A.; Lamine, J.; Ait nouh, F.; Oufni, L.

    2000-01-01

    A method based on using solid state nuclear track detectors (SSNTD) CR- 39 and LR-115 type II and calculating the probabilities for the alpha particles emitted by the uranium and thorium series to reach and be registered on these films was utilized for uranium and thorium contents determination in various geological samples. The distribution of uranium and thorium in different volcanic rocks has been investigated using the track fission method. In this work, the uranium and thorium contents have been determined in different volcanic rock samples by using CR-39 and LR-115 type II solid state nuclear track detectors (SSNTD). The mean critical angles of etching of the solid state nuclear track detectors utilized have been calculated. A petrographical study of the volcanic rock thin layers studied has been conducted. The uranium and thorium distribution inside different rock thin layers has been studied. The mechanism of inclusion of the uranium and thorium nuclei inside the volcanic rock samples studied has been investigated. (author)

  8. Self-determination and economic development. The storage of used nuclear fuel. Community consultation and participation

    International Nuclear Information System (INIS)

    Ahenakew, R.

    1994-01-01

    The Meadow Lake First Nations are a group of small native communities in the Meadow Lake region of northern Saskatchewan. Linguistically and culturally, they are divided into Cree and Dene. The Meadow Lake Tribal Council is studying nuclear fuel waste disposal as a possible route to economic development for the area. No decision will be taken until after the Federal Environmental Assessment Review. The study is proving to be of educational value and interest for the communities

  9. A protocol to determine the situation of nuclear medicine in Venezuela, 1999-2000

    International Nuclear Information System (INIS)

    Carrizales, L.; Leandro, G.

    2001-01-01

    This paper presents preliminary results and the methodology followed for the implementation of a Protocol that included Radiological Protection and Quality Control at SPECT Systems in two important public hospitals at Republica Bolivariana de Venezuela. We found in these inspections that the main problems were the lack of medical physicist capacity in nuclear medicine that implemented programs of quality assurance as well as radiation protection in these departments. (author)

  10. Determination of reliability criteria for standby diesel generators at a nuclear power station

    International Nuclear Information System (INIS)

    Evans, M.G.K.

    1987-01-01

    The requirement for standby diesel generators at nuclear power stations is developed and a probabilistic approach used to define the reliability parameters. The present criteria used when ordering a diesel generator are compared with the testing required by the regulatory body and the most likely requirement following an accident. The impact of this on the diesels at a particular station and the root cause of failures are discussed. (orig.)

  11. Determination of possible damage/degradation of the Sandia National Laboratories Personal Nuclear Accident Dosimeter (PNAD)

    International Nuclear Information System (INIS)

    Potter, Charles Augustus; Ward, Dann C.

    2008-01-01

    This report describes the results of an inspection performed on the existing stock of SNL Personal Nuclear Accident Dosimeters (PNADs). The current stock is approximately 20 years old, and has not been examined since their initial acceptance. A small random sample of PNADs were opened (a destructive process) and the contents visually examined. Sample contents were not degraded and indicate that the existing stock of SNL PNADs is acceptable for continued use

  12. A protocol to determine the situation of nuclear medicine in Venezuela, 1999-2000

    Energy Technology Data Exchange (ETDEWEB)

    Carrizales, L; Leandro, G [Laboratorio Secundario de Calibracion Dosimetrica, Unidad de Tecnologia Nuclear, Instituto Venezolano de Investigaciones Cientificas, Caracas (Venezuela)

    2001-03-01

    This paper presents preliminary results and the methodology followed for the implementation of a Protocol that included Radiological Protection and Quality Control at SPECT Systems in two important public hospitals at Republica Bolivariana de Venezuela. We found in these inspections that the main problems were the lack of medical physicist capacity in nuclear medicine that implemented programs of quality assurance as well as radiation protection in these departments. (author)

  13. Determination of temperature measurements uncertainties of the heat transport primary system of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Pomerantz, Marcelo E.; Coutsiers, Eduardo E.; Moreno, Carlos A.

    1999-01-01

    In this work, the systematic errors in temperature measurements in inlet and outlet headers of HTPS coolant channels of Embalse nuclear power plant are evaluated. These uncertainties are necessary for a later evaluation of the channel power maps transferred to the coolant. The power maps calculated in this way are used to compare power distributions using neutronic codes. Therefore, a methodology to correct systematic errors of temperature in outlet feeders and inlet headers is developed in this work. (author)

  14. Applications of nuclear reaction analysis for determining hydrogen and deuterium distribution in metals

    International Nuclear Information System (INIS)

    Altstetter, C.J.

    1981-01-01

    The use of ion beams for materials analysis has made a successful transition from the domain of the particle physicist to that of the materials scientist. The subcategory of this field, nuclear reaction analysis, is just now undergoing the transition, particularly in applications to hydrogen in materials. The materials scientist must locate the nearest accelerator, because now he will find that using it can solve mysteries that do not yield to other techniques. 9 figures

  15. Nuclear localization of the dehydrin OpsDHN1 is determined by histidine-rich motif

    Science.gov (United States)

    Hernández-Sánchez, Itzell E.; Maruri-López, Israel; Ferrando, Alejandro; Carbonell, Juan; Graether, Steffen P.; Jiménez-Bremont, Juan F.

    2015-01-01

    The cactus OpsDHN1 dehydrin belongs to a large family of disordered and highly hydrophilic proteins known as Late Embryogenesis Abundant (LEA) proteins, which accumulate during the late stages of embryogenesis and in response to abiotic stresses. Herein, we present the in vivo OpsDHN1 subcellular localization by N-terminal GFP translational fusion; our results revealed a cytoplasmic and nuclear localization of the GFP::OpsDHN1 protein in Nicotiana benthamiana epidermal cells. In addition, dimer assembly of OpsDHN1 in planta using a Bimolecular Fluorescence Complementation (BiFC) approach was demonstrated. In order to understand the in vivo role of the histidine-rich motif, the OpsDHN1-ΔHis version was produced and assayed for its subcellular localization and dimer capability by GFP fusion and BiFC assays, respectively. We found that deletion of the OpsDHN1 histidine-rich motif restricted its localization to cytoplasm, but did not affect dimer formation. In addition, the deletion of the S-segment in the OpsDHN1 protein affected its nuclear localization. Our data suggest that the deletion of histidine-rich motif and S-segment show similar effects, preventing OpsDHN1 from getting into the nucleus. Based on these results, the histidine-rich motif is proposed as a targeting element for OpsDHN1 nuclear localization. PMID:26442018

  16. Nuclear localization of the dehydrin OpsDHN1 is determined by histidine-rich motif

    Directory of Open Access Journals (Sweden)

    Itzell Euridice Hernández-Sánchez

    2015-09-01

    Full Text Available The cactus OpsDHN1 dehydrin belongs to a large family of disordered and highly hydrophilic proteins known as Late Embryogenesis Abundant (LEA proteins, which accumulate during the late stages of embryogenesis and in response to abiotic stresses. Herein, we present the in vivo OpsDHN1 subcellular localization by N-terminal GFP translational fusion; our results revealed a cytoplasmic and nuclear localization of the GFP::OpsDHN1 protein in Nicotiana benthamiana epidermal cells. In addition, dimer assembly of OpsDHN1 in planta using a Bimolecular Fluorescence Complementation (BiFC approach was demonstrated. In order to understand the in vivo role of the histidine-rich motif, the OpsDHN1-ΔHis version was produced and assayed for its subcellular localization and dimer capability by GFP fusion and BiFC assays, respectively. We found that deletion of the OpsDHN1 histidine-rich motif restricted its localization to cytoplasm, but did not affect dimer formation. In addition, the deletion of the S-segment in the OpsDHN1 protein affected its nuclear localization. Our data suggest that the deletion of histidine-rich motif and S-segment show similar effects, preventing OpsDHN1 from getting into the nucleus. Based on these results, the histidine rich motif is proposed as a targeting element for OpsDHN1 nuclear localization.

  17. Right Size Determining the Staff Necessary to Sustain Simulation and Computing Capabilities for Nuclear Security

    Energy Technology Data Exchange (ETDEWEB)

    Nikkel, Daniel J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Meisner, Robert [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2010-09-10

    The Advanced Simulation and Computing Campaign, herein referred to as the ASC Program, is a core element of the science-based Stockpile Stewardship Program (SSP), which enables assessment, certification, and maintenance of the safety, security, and reliability of the U.S. nuclear stockpile without the need to resume nuclear testing. The use of advanced parallel computing has transitioned from proof-of-principle to become a critical element for assessing and certifying the stockpile. As the initiative phase of the ASC Program came to an end in the mid-2000s, the National Nuclear Security Administration redirected resources to other urgent priorities, and resulting staff reductions in ASC occurred without the benefit of analysis of the impact on modern stockpile stewardship that is dependent on these new simulation capabilities. Consequently, in mid-2008 the ASC Program management commissioned a study to estimate the essential size and balance needed to sustain advanced simulation as a core component of stockpile stewardship. The ASC Program requires a minimum base staff size of 930 (which includes the number of staff necessary to maintain critical technical disciplines as well as to execute required programmatic tasks) to sustain its essential ongoing role in stockpile stewardship.

  18. Determinants of intention to leave among non-medical employees after a nuclear disaster: a cross-sectional study.

    Science.gov (United States)

    Takeda, Saeka; Orita, Makiko; Fukushima, Yoshiko; Kudo, Takashi; Takamura, Noboru

    2016-07-19

    To conduct a survey among non-medical employees working at the time of the Fukushima Daiichi Nuclear Power Station accident, in order to determine the factors associated with their intentions to leave their jobs during the nuclear disaster. We asked 287 employees (166 men and 121 women) in the study. We asked about their intentions to leave their jobs after the nuclear disaster. We also asked about relevant factors, including the participants' demographic factors, living situations and working environments. We found that in employees younger than 40 (OR=4.73, 95% CI 1.74 to 12.85, p=0.002), being married (OR=3.18, 95% CI 1.03 to 9.79, p=0.044), measurements of the ambient dose rates in their homes after the accident (OR=5.32, 95% CI 1.65 to 17.14, p=0.005), anxiety about their relationships with their colleagues after the accident (OR=3.91, 95% CI 1.51 to 10.16, p=0.005) and the influence of radiation on the workplace (OR=0.33, 95% CI 0.14 to 0.80, p=0.014) were independently associated with the non-medical employees' intentions to leave their jobs after the nuclear disaster. Our results suggest the need for continuous risk communication regarding such factors and the provision of information about the health effects of radiation exposure to non-medical employees after nuclear disasters. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

  19. Spectrophotometric determination of nitrite based on its catalytic effect on the reaction of nuclear fast red and potassium bromate

    Directory of Open Access Journals (Sweden)

    HASSAN ZAVVAR MOUSAVI

    2009-08-01

    Full Text Available A highly selective and sensitive catalytic spectrophotometric method was developed for the determination of nitrite in water samples. The method is based on its catalytic effect on the nuclear fast red–potassium bromate redox reaction in acidic medium. The reaction was followed spectrophotometrically by measuring the change in the absorbance at 518 nm of nuclear fast red 5 min after initiation of the reaction. In this study, the experimental parameters were optimized and the effects of other cations and anions on the determination of nitrite were examined. The calibration graph was linear in the range 2.0–45 µg mL-1 of nitrite. The relative standard deviations for the determination of 15 and 30 µg mL-1 of nitrite were 3.1 and 1.75 %, respectively (n = 8. The detection limit calculated from three times the standard deviation of the blank 3Sb was 0.7 µg mL-1. The method was successfully applied to the determination of nitrite in spiked tap, natural and wastewater samples.

  20. Determination of the impurities Al, Mn, Fe, Ni, Cu and Zn in nuclear grade uranium by ICP-OES

    Energy Technology Data Exchange (ETDEWEB)

    Kakazu, Mauricio H.; Cotrim, Marycel E.B.; Silva, Douglas B. da; Pires, Maria Aparecida F., E-mail: mhkakazu@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Uranium compounds are specially produced for use in nuclear reactors and must meet strict physical and chemicals specifications. The current study discusses the separation of Al, Mn, Fe, Ni, Cu and Zn from uranium compounds and their quantitative determination using inductively coupled plasma optical emission spectrometry. To avoid interference effect caused by uranium in the spectroscopic emission lines of elements of interest, the chromatographic behavior of TBP impregnated macroporous Amberlite XAD-4 column was investigated. The break through curves of uranium obtained showed maximum retention of up to 11 grams of uranium and the elution curves for the elements showed reproducible recovery rate of 90% on 50 mL elution. Synthetic samples of nuclear grade uranium prepared with the addition of 250 {mu}g/g of U of the above individual elements were used to verify the performance of the method. The method showed a recovery rate of 80 to 90% for the elements under study. (author)

  1. Determination of the impurities Al, Mn, Fe, Ni, Cu and Zn in nuclear grade uranium by ICP-OES

    International Nuclear Information System (INIS)

    Kakazu, Mauricio H.; Cotrim, Marycel E.B.; Silva, Douglas B. da; Pires, Maria Aparecida F.

    2011-01-01

    Uranium compounds are specially produced for use in nuclear reactors and must meet strict physical and chemicals specifications. The current study discusses the separation of Al, Mn, Fe, Ni, Cu and Zn from uranium compounds and their quantitative determination using inductively coupled plasma optical emission spectrometry. To avoid interference effect caused by uranium in the spectroscopic emission lines of elements of interest, the chromatographic behavior of TBP impregnated macroporous Amberlite XAD-4 column was investigated. The break through curves of uranium obtained showed maximum retention of up to 11 grams of uranium and the elution curves for the elements showed reproducible recovery rate of 90% on 50 mL elution. Synthetic samples of nuclear grade uranium prepared with the addition of 250 μg/g of U of the above individual elements were used to verify the performance of the method. The method showed a recovery rate of 80 to 90% for the elements under study. (author)

  2. Analysis of the gas outlets of the nuclear power plants relation between nuclides determined by gamma-spectrometry

    International Nuclear Information System (INIS)

    Mihalik, J.

    2008-01-01

    The National Radiation Protection Institute is interested in the long-time study of the noble gases outlets of nuclear power plants. One of the causes of monitoring the gas outlet is independent assessment of the influence nuclear power plant on the environment. Result of this analysis confirms the correlation between 88 Kr and 85m Kr in all technological compartments. Except the internal flue of the first production unit, the high correlation coefficient was determined between 88 Kr - 135 Xe and 85m Kr - 135 Xe. The analysis presented by this paper suggests that the highest correlation coefficient was always reached between 88 Kr and 85 mKr. Its values approached to 1. Similar results were confirmed between 85m Kr - 135 Xe and 88 Kr - 1 35 Xe. As far as the ratio of the specific activity concerns, we found certain congruence between 2006 and 2007. (authors)

  3. Determination of nuclear fuel burn-up using mass spectrometric techniques

    International Nuclear Information System (INIS)

    Saha, B.; Bagyalakshmi, R.; Periaswami, G.; Kavimandan, V.D.; Chitambar, S.A.; Jain, H.C.; Mathews, C.K.

    1977-01-01

    Determination of burn-up using a stable fission product monitor such as 148 Nd and heavy elements, determined by isotope dilution mass spectrometry gives the most accurate data. This report describes the work carried out to standardise the conditions for burn-up determination. Some typical results are given. (author)

  4. Determination of solid- and liquid-phase gastric emptying half times in cats by use of nuclear scintigraphy.

    Science.gov (United States)

    Costello, M; Papasouliotis, K; Barr, F J; Gruffydd-Jones, T J; Caney, S M

    1999-10-01

    To use nuclear scintigraphy to establish a range of gastric emptying half times (t1/2) following a liquid or solid meal in nonsedated cats. 12 clinically normal 3-year-old domestic shorthair cats. A test meal of 75 g of scrambled eggs labeled with technetium Tc 99m tin colloid was fed to 10 of the cats, and solid-phase gastric emptying t1/2 were determined by use of nuclear scintigraphy. In a separate experiment, 8 of these cats plus an additional 2 cats were fed 18 ml (n = 5) or 36 ml (n = 5) of a nutrient liquid meal labeled with technetium Tc 99m pentetate. Liquid-phase gastric emptying t1/2 then were determined by use of scintigraphy. Solid-phase gastric emptying t1/2 were between 210 and 769 minutes (median, 330 minutes). Median liquid-phase gastric emptying t1/2 after ingestion of 18 or 36 ml of the test meal were 67 minutes (range, 60 to 96 minutes) and 117 minutes (range, 101 to 170 minutes), respectively. The median t1/2 determined for cats receiving 18 ml of the radiolabeled liquid was significantly less than that determined for cats receiving 36 ml of the test meal. The protocol was tolerated by nonsedated cats. Solid-phase gastric emptying t1/2 were prolonged, compared with liquid-phase t1/2, and a major factor governing the emptying rate of liquids was the volume consumed. Nuclear scintigraphy may prove useful in assessing gastric motility disorders in cats.

  5. Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1978-September 30, 1979

    International Nuclear Information System (INIS)

    Waterbury, G.R.

    1980-03-01

    Work continues on the development of dissolution techniques for difficult-to-dissolve nuclear materials, the development of methods and automated instruments for plutonium, uranium, and thorium determinations, and the preparation of plutonium materials for the Safeguards Analytical Laboratory Evaluation (SALE) program and distribution by the National Bureau of Standards (NBS) as standard reference materials (SRMs). We are measuring the loner plutonium isotope half-lives, evaluating the isotope correlation techniques and the chemistry involved in the mass-spectrometric ion-bead techniques, and analyzing the SALE uranium materials. Completed subtasks include evaluations of various Teflon materials to recommend those acceptable for the dissolution apparatus developed at LASL, investigations of laser-enhanced dissolution of refractory materials, determinations of diverse ion effects on the microgram-sensitive method for determining uranium, fabrication of the first automated controlled-potential coulometric analyzer for determining plutonium, preparation of a 244 Pu material for distribution by NBS as a SRM, and determination of the half-life of 239 Pu. Work has been started on a spectrophotometric method for determining microgram quantities of plutonium, a microcomplexometric titration method for determining uranium, the use of new reagents for separations of plutonium, the preparation and packaging of a new lot of high-purity plutonium metal for distribution by NBS as a plutonium chemical SRM, and determination of half-lives of other plutonium isotopes

  6. Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1978-September 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Waterbury, G.R. (comp.)

    1980-03-01

    Work continues on the development of dissolution techniques for difficult-to-dissolve nuclear materials, the development of methods and automated instruments for plutonium, uranium, and thorium determinations, and the preparation of plutonium materials for the Safeguards Analytical Laboratory Evaluation (SALE) program and distribution by the National Bureau of Standards (NBS) as standard reference materials (SRMs). We are measuring the loner plutonium isotope half-lives, evaluating the isotope correlation techniques and the chemistry involved in the mass-spectrometric ion-bead techniques, and analyzing the SALE uranium materials. Completed subtasks include evaluations of various Teflon materials to recommend those acceptable for the dissolution apparatus developed at LASL, investigations of laser-enhanced dissolution of refractory materials, determinations of diverse ion effects on the microgram-sensitive method for determining uranium, fabrication of the first automated controlled-potential coulometric analyzer for determining plutonium, preparation of a /sup 244/Pu material for distribution by NBS as a SRM, and determination of the half-life of /sup 239/Pu. Work has been started on a spectrophotometric method for determining microgram quantities of plutonium, a microcomplexometric titration method for determining uranium, the use of new reagents for separations of plutonium, the preparation and packaging of a new lot of high-purity plutonium metal for distribution by NBS as a plutonium chemical SRM, and determination of half-lives of other plutonium isotopes.

  7. Determination of total plutonium content in spent nuclear fuel assemblies with the differential die-away self-interrogation instrument

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, Alexis C. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87544 (United States); Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 500 S State St., Ann Arbor, MI 48109 (United States); Henzl, Vladimir; Menlove, Howard O.; Swinhoe, Martyn T.; Belian, Anthony P. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87544 (United States); Flaska, Marek; Pozzi, Sara A. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 500 S State St., Ann Arbor, MI 48109 (United States)

    2014-11-11

    As a part of the Next Generation Safeguards Initiative Spent Fuel project, we simulate the response of the Differential Die-away Self-Interrogation (DDSI) instrument to determine total elemental plutonium content in an assayed spent nuclear fuel assembly (SFA). We apply recently developed concepts that relate total plutonium mass with SFA multiplication and passive neutron count rate. In this work, the multiplication of the SFA is determined from the die-away time in the early time domain of the Rossi-Alpha distributions measured directly by the DDSI instrument. We utilize MCNP to test the method against 44 pressurized water reactor SFAs from a simulated spent fuel library with a wide dynamic range of characteristic parameters such as initial enrichment, burnup, and cooling time. Under ideal conditions, discounting possible errors of a real world measurement, a root mean square agreement between true and determined total Pu mass of 2.1% is achieved.

  8. Development of destructive methods of burn-up determination and their application on WWER type nuclear fuels

    International Nuclear Information System (INIS)

    Hermann, A.; Stephan, H.; Nebel, D.

    1984-03-01

    Results are described of a cooperation between the Central Institute of Nuclear Research Rossendorf and the Radium Institute 'V.G. Chlopin' Leningrad in the field of destructive burn-up determination. Laboratory methods of burn-up determination using the classical monitors 137 Cs, 106 Ru, 148 Nd and isotopes of heavy metals (U, Pu) as well as the usefulness of 90 Sr, stable isotopes of Ru and Mo as monitors are dealt with. The analysis of the fuel components uranium (spectrophotometry, potentiometric titration, mass-spectrometric isotope dilution) and plutonium (spectrophotometry, coulometric titration, mass- and alpha-spectrometric isotope dilution) is fully described. Possibilities of increasing the reproducibility (automatic adjusting of measurement conditions) and the sensibility (ion impuls counting) of mass-spectrometric measurements are proposed and applied to a precise determination of Am and Cm isotopic composition. The methods have been used for burn-up analysis of spent WWER (especially WWER-440) fuel. (author)

  9. Description of apparatus for determining radiological source terms of nuclear fuels

    International Nuclear Information System (INIS)

    Baldwin, D.L.; Woodley, R.E.; Holt, F.E.; Archer, D.V.; Steele, R.T.; Whitkop, P.G.

    1985-01-01

    New apparatus have been designed, built and are currently being employed to measure the release of volatile fission products from irradiated nuclear fuel. The system is capable of measuring radiological source terms, particularly for cesium-137, cesium-134, iodine-129 and krypton-85, in various atmospheres at temperatures up to 1200 0 C. The design allows a rapid transient heatup from ambient to full temperature, a hold at maximum temperature for a specified period, and rapid cooldown. Released fission products are measured as deposition on a platinum thermal gradient tube or in a filter/charcoal trap. Noble gases pass through to a multi-channel gamma analyzer. 1 ref., 4 figs

  10. The ''healthy worker effect'' and other determinants of mortality in workers in the nuclear industry

    International Nuclear Information System (INIS)

    Beral, V.; Carpenter, L.; Booth, M.; Inskip, H.; Brown, A.

    1987-01-01

    Workers in the nuclear industry has been found to have lower mortality rates than the national average. This is in part due to the ''healthy worker effect'' - the recruitment of healthy individuals into the workforce. Employees of the United Kingdom Atomic Energy Authority had especially low mortality rates in the 15 years following first employment. Thereafter mortality rates remained about 20% below the national average. Social class was a clear predictor of mortality, the professional and executive classes (Social Classes I and II) having mortality rates about 40% below the national average. Mortality was not related to duration of employment. Radiation and non-radiation workers generally showed similar patterns of mortality. (author)

  11. Determination of the radioiodine species in the exhaust air of nuclear facilities

    International Nuclear Information System (INIS)

    Deuber, H.

    1977-01-01

    Using the selective I 2 sorption materials DSM 10 and DSM 11 measurements were performed with radioiodine species samplers in the exhaust air of a research reactor and of several nuclear power stations (BWR, PWR). The radioiodine species samplers were used upstream and downstream of iodine filters (containment exhaust air stand-by filter, shutoff room exhaust air filter) as well as in the exhaust air of the stack. The results obtained by use of DSM 10 and DSM 11 generally agreed. The percentage of aerosol iodine was low in all cases ( [de

  12. Determination of stability of saturated sands of Bredasdorp and Varswater Formations: Koeberg nuclear power station

    International Nuclear Information System (INIS)

    De Witt, M.J.; Barker, O.B.

    1985-01-01

    The planning of the Koeberg nuclear power station was postulated on the basis of possible seismic ground movements of sufficient intensity to cause liquefaction of the sand overlying the bedrock. Where seismic instability may occur, it is normally necessary for the potentially liquefiable soils to be removed and replaced with a stable material. The site investigations were therefore designed to evaluate the soils parameters necessary for the safe excavation of sand. The properties of potential backfill materials were studied and requirements for selective stockpiling of material from the excavation defined

  13. Determination of elements in concrete of a nuclear accelerator to dismantle, by instrumental neutron activation analysis, ICPMS and ICPAES

    International Nuclear Information System (INIS)

    Gaudry, A.; Bertho, X.; Piccot, D.; Fougeron, C.

    1998-01-01

    The distribution of radionuclides and their radioactivity in irradiated waste concrete are modelled using the characteristics of nuclear particle fluxes integrated all during the life-time of the installation, chemical composition of the material, and activation parameters of nuclear reactions produced by particles and secondary neutrons on elements. This paper describes the techniques used for determining the chemical composition of trace elements radioactivated by neutrons and particles, but also the major elements which act upon the neutron penetration into the depth of the concrete. Major elements were determined using mainly, Inductively Coupled Plasma-Atomic Emission Spectroscopy (ICP-AES) for Si, Al, Fe, Mn, Mg, Ca, Na, K, Ti, P and Instrumental Neutron Activation Analysis (INAA) for Al, Mn, Fe, Mg, Ca, Ba, Na, K, and other specific methods for C, O, S, and H. Trace elements were also determined using Inductively Coupled Plasma Mass Spectrometry (ICP-MS) and INAA. Forty five elements were determined. When present, solid iron was separated by a magnetic bar after previous breaking of the concrete. The concrete was powdered to a granulometry of less than 0.5 mm for INAA and homogenized. Iron was determined separately by INAA. For the determinations by ICP-AES and ICP-MS, powders were previously fused by means of LiBO 2 , then dissolved in dilute HNO 3 before analysis. A comparison between the results obtained, on the one hand, by ICP-AES and INAA, on the second hand, by ICP-MS and INAA revealed generally a very good agreement, making consistent analytical results

  14. Contract-related dose determination in the Biblis nuclear power station of the RWE

    International Nuclear Information System (INIS)

    Kallmeyer, D.; Ambros, R.

    1979-01-01

    An important method of control (and hence reduction) of the exposure to radiation is the work- or contract-related dosage determination. (ADOS). The aim of ADOS in the detailed determination of the dosage to which personnel is exposed during all operations in the controlled area, and the allocation of this dosage to the operations in the controlled zone. The authors describe the methodology and give selected results from a computerised acquisition system for the contract-related dosage determination. (orig.) [de

  15. One procedure for determination of the neutron flux in the nuclear reactor fuel

    International Nuclear Information System (INIS)

    Bulovic, V.; Krtil, J.; Maksimovic, Z.; Martinc, R.

    1979-09-01

    Possibility of determination of the neutron flux in the fuel of a heavy water reactor has been examined. In determination of the flux an iterative procedure was used to compare calculated and measured contents of several fission products. The former contents were determined by calculation of the burning process balance and the latter by non-destructive gamma-spectrometric analysis of fuel. The obtained results prove the possibility of such determination of not only the average value of the flux but also of the change of its intensity during utilization of fuel (author) [sr

  16. Application of adsorptive stripping voltammetry to the simultaneous determination of bismuth and copper in the presence of nuclear fast red

    International Nuclear Information System (INIS)

    Gholivand, M.B.; Romiani, A.A.

    2006-01-01

    A sensitive and selective method for the simultaneous determination of copper and bismuth by adsorptive stripping was developed using nuclear fast red (2-anthracenesulfonic acid, 4-amino-9,10-dihydro-1,3-dihydroxy-9,10-dioxo-, monosodium salt) as selective complexing agent onto hanging mercury drop electrode. In a single scan both metals gave peaks that were distinctly separated by 85 mV allowing their determination in the presence of each other. Optimal analytical conditions were found to be: nuclear fast red concentration of 80 μM, pH of 2.8 and adsorptive potential of -300 mV versus Ag/AgCl. With accumulation time of 180 s the peaks currents are proportional to concentration of copper and bismuth over the 1-100 and 5-60 ng mL -1 range with detection limits of 0.2 and 1.2 ng mL -1 , respectively. The procedure was applied to simultaneous determination of copper and bismuth in some real samples

  17. Determination of safe radioactive releases to the atmosphere from the nuclear power site, Dynefontein

    International Nuclear Information System (INIS)

    Basson, J.K.; Van As, D.

    1976-01-01

    South Africa's first nuclear power station, Koeberg A, is to be built by Escom at Dynefontein, 28 km north of Cape Town, and the experience gained at the National Nuclear Research Centre, Pelindaba, has been used by the AEB as basis for the pre-operational investigation. The capacity of the environment to accept airborne radioactive effluent safely depends on various local factors such as dispersion conditions, the ecology, the habits of the local population and the accumulation, through critical pathways, of pertinent radionuclides. Long-term average dilution factors at varying distances from a 100m stack have been calculated by ESCOM from mesometeorological data collected by the CSIR. On the basis of available data, permissible release rates are derived for radioisotopes of the noble gases (critical pathway:external cloud exposure), 131 I, 137 Cs, 106 Ru, 125 Sb and 114 Ce and tritium. Although final confirmation of these values can only be obtained after operation, such a pre-operational survey may serve as an example to conventional industry [af

  18. Genetic polymorphisms of Echinococcus tapeworms in China as determined by mitochondrial and nuclear DNA sequences ✩

    Science.gov (United States)

    Nakao, Minoru; Li, Tiaoying; Han, Xiumin; Ma, Xiumin; Xiao, Ning; Qiu, Jiamin; Wang, Hu; Yanagida, Tetsuya; Mamuti, Wulamu; Wen, Hao; Moro, Pedro L.; Giraudoux, Patrick; Craig, Philip S.; Ito, Akira

    2009-01-01

    The genetic polymorphisms of Echinococcus spp. in the eastern Tibetan Plateau and the Xinjiang Uyghur Autonomous Region were evaluated by DNA sequencing analyses of genes for mitochondrial cytochrome c oxidase subunit 1 (cox1) and nuclear elongation factor-1 alpha (ef1a). We collected 68 isolates of Echinococcus granulosus sensu stricto (s.s.) from Xinjiang and 113 isolates of E. granulosus s. s., 49 isolates of Echinococcus multilocularis and 34 isolates of Echinococcus shiquicus from the Tibetan Plateau. The results of molecular identification by mitochondrial and nuclear markers were identical, suggesting the infrequency of introgressive hybridization. A considerable intraspecific variation was detected in mitochondrial cox1 sequences. The parsimonious network of cox1 haplotypes showed star-like features in E. granulosus s. s. and E. multilocularis, but a divergent feature in E. shiquicus. The cox1 neutrality indexes computed by Tajima's D and Fu's Fs tests showed high negative values in E. granulosus s. s. and E. multilocularis, indicating significant deviations from neutrality. In contrast, the low positive values of both tests were obtained in E. shiquicus. These results suggest the following hypotheses: (i) recent founder effects arose in E. granulosus and E. multilocularis after introducing particular individuals into the endemic areas by anthropogenic movement or natural migration of host mammals, and (ii) the ancestor of E. shiquicus was segregated into the Tibetan Plateau by colonizing alpine mammals and its mitochondrial locus has evolved without bottleneck effects. PMID:19800346

  19. Determination of the magnetic impurities contribution to the nuclear relaxation in metals

    International Nuclear Information System (INIS)

    Cohen, A.M.

    1982-01-01

    The renormalization group techniques developed by Wilson for the Kondo problem are applied, for the first time, to the calculation of nuclear spin relaxation rates in dilute magnetic alloys. A procedure that calculates the longitudinal relaxation time T 1 over the entire temperature range 0 B T 1 is derived; for distances R between the impurity and the nucleus large compared to the inverse Fermi momentum H f , the result is identical to Korringa's expression for the nuclear spin relaxation rate in the pure metal. For smaller k F R, T 1 increases and becomes infinite as k F R→0. A numerical approach, capable of calculating T 1 at finite temperatures, is presented and tested by calculating T 1 for T→0; the numerical results are in excellent agreement with the analytical expression discussed above. Only for k F R→ infinity do the results for T 1 at T=0 agree with those found by Roshen and Saam, who recently analysed this problem in the light of Nozieres's Fermi liquid theory. The reasons for the discrepancy for finite k F R are discussed. (author) [pt

  20. Determination of bound and unbound water in dental alginate irreversible hydrocolloid by nuclear magnetic resonance spectroscopy.

    Science.gov (United States)

    Fellows, C M; Thomas, G A

    2009-04-01

    Alginate materials are considered unsuitable for precise fixed prosthetic rehabilitation due to their tendency to undergo spontaneous syneresis. Commercial alginate impression materials were investigated using Nuclear Magnetic Resonance (NMR) Spectroscopy to probe the relation between changes in the microscopic water environment and dimensional change to obtain a better understanding of spontaneous syneresis. NMR was used to measure the spin-lattice relaxation times (T(1)) of (1)H nuclei in water in alginate matrices to characterize changes in gel structure over time. These results were related to the dimensional stabilities of the alginate impression materials, their chemical compositions, and the Moisture Sorption Isotherms (MSI) obtained by incubation at fixed relative humidities. The rate of change of T(1) with time was found to be a better predictor of dimensional stability than MSI. The greatest dimensional stability for the alginate powders investigated was associated with a high filler:alginate ratio and a high Ca:Na ratio. Nuclear magnetic resonance spectroscopy may used to measure changes in alginate impression materials under conditions where no dimensional change can be observed directly. Changes occurred rapidly even at 100% humidity, suggesting the dimensional stability of alginate impression materials is partially independent of the rate of dehydration. The results may open a way to formulate alginate impression materials more suitable for precise fabrication of dental prostheses.

  1. A methodology for determining the dynamic exchange of resources in nuclear fuel cycle simulation

    Energy Technology Data Exchange (ETDEWEB)

    Gidden, Matthew J., E-mail: gidden@iiasa.ac.at [International Institute for Applied Systems Analysis, Schlossplatz 1, A-2361 Laxenburg (Austria); University of Wisconsin – Madison, Department of Nuclear Engineering and Engineering Physics, Madison, WI 53706 (United States); Wilson, Paul P.H. [University of Wisconsin – Madison, Department of Nuclear Engineering and Engineering Physics, Madison, WI 53706 (United States)

    2016-12-15

    Highlights: • A novel fuel cycle simulation entity interaction mechanism is proposed. • A framework and implementation of the mechanism is described. • New facility outage and regional interaction scenario studies are described and analyzed. - Abstract: Simulation of the nuclear fuel cycle can be performed using a wide range of techniques and methodologies. Past efforts have focused on specific fuel cycles or reactor technologies. The CYCLUS fuel cycle simulator seeks to separate the design of the simulation from the fuel cycle or technologies of interest. In order to support this separation, a robust supply–demand communication and solution framework is required. Accordingly an agent-based supply-chain framework, the Dynamic Resource Exchange (DRE), has been designed implemented in CYCLUS. It supports the communication of complex resources, namely isotopic compositions of nuclear fuel, between fuel cycle facilities and their managers (e.g., institutions and regions). Instances of supply and demand are defined as an optimization problem and solved for each timestep. Importantly, the DRE allows each agent in the simulation to independently indicate preference for specific trading options in order to meet both physics requirements and satisfy constraints imposed by potential socio-political models. To display the variety of possible simulations that the DRE enables, example scenarios are formulated and described. Important features include key fuel-cycle facility outages, introduction of external recycled fuel sources (similar to the current mixed oxide (MOX) fuel fabrication facility in the United States), and nontrivial interactions between fuel cycles existing in different regions.

  2. A methodology for determining the dynamic exchange of resources in nuclear fuel cycle simulation

    International Nuclear Information System (INIS)

    Gidden, Matthew J.; Wilson, Paul P.H.

    2016-01-01

    Highlights: • A novel fuel cycle simulation entity interaction mechanism is proposed. • A framework and implementation of the mechanism is described. • New facility outage and regional interaction scenario studies are described and analyzed. - Abstract: Simulation of the nuclear fuel cycle can be performed using a wide range of techniques and methodologies. Past efforts have focused on specific fuel cycles or reactor technologies. The CYCLUS fuel cycle simulator seeks to separate the design of the simulation from the fuel cycle or technologies of interest. In order to support this separation, a robust supply–demand communication and solution framework is required. Accordingly an agent-based supply-chain framework, the Dynamic Resource Exchange (DRE), has been designed implemented in CYCLUS. It supports the communication of complex resources, namely isotopic compositions of nuclear fuel, between fuel cycle facilities and their managers (e.g., institutions and regions). Instances of supply and demand are defined as an optimization problem and solved for each timestep. Importantly, the DRE allows each agent in the simulation to independently indicate preference for specific trading options in order to meet both physics requirements and satisfy constraints imposed by potential socio-political models. To display the variety of possible simulations that the DRE enables, example scenarios are formulated and described. Important features include key fuel-cycle facility outages, introduction of external recycled fuel sources (similar to the current mixed oxide (MOX) fuel fabrication facility in the United States), and nontrivial interactions between fuel cycles existing in different regions.

  3. Determination of the costs of the nuclear desalination using the DEEP code from IAEA

    International Nuclear Information System (INIS)

    Ramirez S, J.R.; Palacios H, J.C.; Alonso V, G.

    2005-01-01

    The desalination of seawater is being an important solution to satisfy the demands of drinking water to population's centers that have hydric resources very limited, like it is the case of some Arab countries and arid regions of the planet, in where they have settled desalination plants that use as energy source to those fossil fuels or nuclear energy plants. Taking into account that the desalination of seawater is a process that consumes a lot of thermal and/or electric energy, it is necessary to quantify the costs of the supply and that of the desalination plant for different options and technologies, looking for this way the but appropriate for the specific conditions of the region where it has planned the desalination of seawater. In this report the three technologies but promising for the desalination are described and by means of the DEEP code the costs of production of water and energy are evaluated, using as thermal source different types of power nuclear reactors. It was obtained according to DEEP that the costs of the electricity generation for the considered reactors are around 40 USD/MWh. With these costs of electric power generation and using the DEEP code is obtained that the costs of production of drinking water are around 1 USD/m 3 . (Author)

  4. Computer program for Scatchard analysis of protein: Ligand interaction - use for determination of soluble and nuclear steroid receptor concentrations

    International Nuclear Information System (INIS)

    Leake, R.; Cowan, S.; Eason, R.

    1998-01-01

    Steroid receptor concentration may be determined routinely in biopsy samples of breast and endometrial cancer by the competition method. This method yields data for both the soluble and nuclear fractions of the tissue. The data are usually subject to Scatchard analysis. This Appendix describes a computer program written initially for a PDP-11. It has been modified for use with IBM, Apple Macintosh and BBC microcomputers. The nature of the correction for competition is described and examples of the printout are given. The program is flexible and its use for different receptors is explained. The program can be readily adapted to other assays in which Scatchard analysis is appropriate

  5. Determination of 63Ni and 55Fe in nuclear waste samples using radiochemical separation and liquid scintillation counting

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Frøsig Østergaard, L.; Nielsen, S.P.

    2005-01-01

    An analytical method for the determination of Ni-63 and Fe-55 in nuclear waste samples such as graphite, heavy concrete, aluminium and lead was developed. Different decomposition methods (i.e. ashing, acid digestion and alkali fusion) were investigated for the decomposition of the samples...... by extraction chromatography. The purified Ni-63 and Fe-55 was then measured by liquid scintillation counting. The chemical yields of the separation procedures for Fe-55 and Ni-63 are above 90% and the decontamination factors for all interfering radionuclides are more than 10(5). The detection limits...

  6. Case study on the use of PSA methods: Determining safety importance of systems and components at nuclear power plants

    International Nuclear Information System (INIS)

    1991-04-01

    This case study emphasizes the step of probabilistic safety assessment (PSA) regarding identification of systems and components important to nuclear plant safety. An importance analysis involves combining information that is both qualitative and probabilistic in nature to generate a numerical ranking to determine the system and/or component failures that dominate the risk. Such a ranking can suggest where hardware, software, human factors and component design changes can be implemented to improve plant safety. Examples of using ranking methodology are described. A qualitative ranking criteria is discussed for components and systems that are not included in a PSA. 18 refs, 7 figs, 18 tabs

  7. Determination of the details of technical standard concerning the transport of nuclear fuel materials outside the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The determination is defined under the regulations concerning the transport of nuclear fuel materials outside the works or the enterprise. The least dangerous nuclear fuel materials designated by the Director General of Science and Technology Agency include, besides such materials listed and corresponding to the particular terms, natural or depleted uranium, natural thorium and their compounds whose surface is covered by corrosion resistance metal. The permissible density of surface stipulated by the Director is 1/100,000 micro-curie per centi-meter 2 for radioactive substances not emitting alpha rays and 1/10,000 micro-curie per centi-meter 2 for radioactive substances emitting alpha rays. General test conditions of A, BM and BU type of loads are in detail provided for. The nuclear fuel materials defined by the Director not as fission materials are uranium 233 and 235, plutonium 238 or 241, whose quantity or combined quantity of such substances do not exceed 15 grams and natural or depleted uranium. The permissible accumulative dose specified for employees is the figure (unit rem) calculated by the formula D=5 (N-18), when D means the permissible accumulative dose and N number of the age. The permissible exposure dose shall be 3 rem for 3 months for employees and 1.5 rem for a year for persons other than employees. (Okada, K.)

  8. Determination of technical details concerning measures for transportation of nuclear fuel materials in the works or the enterprise

    International Nuclear Information System (INIS)

    1979-01-01

    The determination is defined under the regulation for installation and operation of reactors for power generation. The limit of radioactive concentration of things contaminated by nuclear fuel materials which need not be sealed in a vessel is designated by the Minister of International Trade and Industry as 1/10,000 of A2 value per gram provided by another notification on transport of nuclear fuel materials outside the works. Measures for prevention of hazards shall be taken to stop flying out or leaking of radioactive substances by solidifying them with concrete or other hardening materials, not to let rain water penetrate into or to make each exterior side of transferred cubic things more than 10 centi-meters. The application for permission of things highly difficult to be enclosed in a vessel shall list name and address of the applicant, kind, quantity, form and nature of conveyed things contaminated by nuclear fuel materials, data and route of transfer and measures for prevention of hazards in transport. Radioactive doses specified by the minister are for an hour 200 mili-rem on the surface and 10 mili-rem at the distance of 1 meter from the surface of load, vehicle and container. Radioactive doses for the special loads shall be for an hour 1,000 mili-rem on the surface and 10 mili-rem at the distance of 2 meters from the surface of transferred things. (Okada, K.)

  9. Use of electrothermal atomization for determining metallic impurities in nuclearly pure uranium compounds

    International Nuclear Information System (INIS)

    Franco, M.B.

    1986-01-01

    Atomic absorption spectrometry with electrothermal atomization was used for the determination of Al, Cd, Cr, Fe, Mn, Mo and Ni as impurities in uranium oxide samples. The determinations were performed in solubilized samples both with and without uranium separation as well as in solid samples. (Author) [pt

  10. Determination of spins and radioactive widths of tellurium nuclear levels with capturre gamma rays

    International Nuclear Information System (INIS)

    Bianchini, F.G.

    1973-01-01

    Spins and levels widths of the tellurium, mainly 128 Te and 130 Te, were determinated by gamma spectroscopy. Measurements of inelastic and elastic scattering, angular distribution and scattering temperature dependence, were still made. Energy levels of this isotopes, were also determinated [pt

  11. Use of electrothermal atomization for determining metallic impurities in nuclearly pure uranium compounds

    International Nuclear Information System (INIS)

    Franco, M.B.

    1985-01-01

    Atomic absorption spectrometry with electrothermal atomization was used for the determination of Al, Cd, Cr, Fe, Mn, Mo and Ni as impurities in uranium oxide samples. The determinations were performed in solubilized samples both with and without uranium separation as well as in solid samples. (Author) [pt

  12. Proposed criteria for determining enforcement actions in the regulation of nuclear power plants

    International Nuclear Information System (INIS)

    Amparo, O.L.

    1982-01-01

    This document describes an approach for determining regulatory enforcement actions that would serve as basis for the maintenance of a license. Enforcement actions are determined according to defined severity of violations or failure by the licensee to meet regulatory requirements and license conditions. (ELC)

  13. Contribution to the determination of total hydrogen in oxide nuclear fuels

    International Nuclear Information System (INIS)

    Bartscher, W.; Kutter, H.

    1979-01-01

    Normally the total hydrogen content of a fast breeder mixed oxide fuel is calculated from the results of the determinations of free hydrogen and water. Thermodynamic considerations, coupled with kinetic results for room temperature and 1000 0 C and taken from the literature indicate, that the normal method for the determination of water by heating in a carrier gas stream and subsequent coulometric determination of the expelled water must give low results. A modification of this method involving the introduction of a copper oxide furnace into the system for the oxidation of hydrogen has been studied. The resulting method for the determination of total hydrogen gives about ten times higher values than those calculated from the normal water determination. These total hydrogen values and the oxygen to metal ratios which are obtained by gravimetric methods and not corrected for the water content, reflect more realistically the in-pile conditions in the fuel pin. (Auth.)

  14. Determination of alpha dose rate profile at the HLW nuclear glass/water interface

    Energy Technology Data Exchange (ETDEWEB)

    Mougnaud, S., E-mail: sarah.mougnaud@cea.fr [CEA Marcoule, DEN/DTCD/SECM, BP 17171, 30207 Bagnols-sur-Cèze cedex (France); Tribet, M.; Rolland, S. [CEA Marcoule, DEN/DTCD/SECM, BP 17171, 30207 Bagnols-sur-Cèze cedex (France); Renault, J.-P. [CEA Saclay, NIMBE UMR 3685 CEA/CNRS, 91191 Gif-sur-Yvette cedex (France); Jégou, C. [CEA Marcoule, DEN/DTCD/SECM, BP 17171, 30207 Bagnols-sur-Cèze cedex (France)

    2015-07-15

    Highlights: • The nuclear glass/water interface is studied. • The way the energy of alpha particles is deposited is modeled using MCNPX code. • A model giving dose rate profiles at the interface using intrinsic data is proposed. • Bulk dose rate is a majoring estimation in alteration layer and in surrounding water. • Dose rate is high in small cracks; in larger ones irradiated volume is negligible. - Abstract: Alpha irradiation and radiolysis can affect the alteration behavior of High Level Waste (HLW) nuclear glasses. In this study, the way the energy of alpha particles, emitted by a typical HLW glass, is deposited in water at the glass/water interface is investigated, with the aim of better characterizing the dose deposition at the glass/water interface during water-induced leaching mechanisms. A simplified chemical composition was considered for the nuclear glass under study, wherein the dose rate is about 140 Gy/h. The MCNPX calculation code was used to calculate alpha dose rate and alpha particle flux profiles at the glass/water interface in different systems: a single glass grain in water, a glass powder in water and a water-filled ideal crack in a glass package. Dose rate decreases within glass and in water as distance to the center of the grain increases. A general model has been proposed to fit a dose rate profile in water and in glass from values for dose rate in glass bulk, alpha range in water and linear energy transfer considerations. The glass powder simulation showed that there was systematic overlapping of radiation fields for neighboring glass grains, but the water dose rate always remained lower than the bulk value. Finally, for typical ideal cracks in a glass matrix, an overlapping of irradiation fields was observed while the crack aperture was lower than twice the alpha range in water. This led to significant values for the alpha dose rate within the crack volume, as long as the aperture remained lower than 60 μm.

  15. Discriminant analysis of characteristics determining acceptance or rejection of nuclear power

    International Nuclear Information System (INIS)

    Holsapple, C.W.; Whinston, A.B.

    1977-01-01

    This study utilizes the linear discriminant model to analyze demographic and attitudinal data concerning the construction of a nuclear power facility at the Bailly site in northern Indiana. The objective is to ascertain the extent to which various respondent characteristics are useful in distinguishing among respondent attitudes (opposed, in favor, unsure) toward the Bailly project. Examination of reduced space characteristics leads the authors to postulate an interpretation of its two dimensions as respondent uncertainty and respondent resistance. The largest contributor (positive) to uncertainty was found to be a divorced or separated marital status; the greatest contributer (negative) to resistance was found to be home ownership. Both of these respondent characteristics were significant in the univariate sense. A particularly striking trend was the reliance of the opposed group upon electronic media as the source of most local news, whereas the other two groups tended to rely most heavily on newspapers

  16. Determination of 89Sr and 90Sr in highly radioactive water from a nuclear power plant

    International Nuclear Information System (INIS)

    Bojanowski, R.; Radecki, Z.; Duniec, S.

    1994-01-01

    The main criterion in assaying strontium radionuclides is to obtain radiochemically pure strontium sources for beta-particle counting. Nuclear power plant waters contain both 89 Sr and 90 Sr accompanied by many beta-particle and gamma-ray emitting fission and neutron-activation products. The latter activities can sometimes exceed those of strontium by a factor of 10 7 . Efficient purification procedures must be used to remove these products, preferably at an initial stage of analysis to reduce the radiation risk to personnel. A method has been developed in which a water sample is passed through a prefilter installed on top of an ion-exchange column filled with Dowex-50 resin in H + form. This prefilter is impregnated with ferrocyanides and manganese dioxide and retains most of the interfering radionuclides while the underlying cation-exchanger takes up strontium ions. A few additional purification steps result in a strontium salt that is free from other radioactivity. (orig.)

  17. Gamma-ray induced Doppler broadening and the determination of lifetimes of excited nuclear states

    International Nuclear Information System (INIS)

    Boerner, H.G.; Jolie, J.; Robinson, S.J.; Kessler, E.G.; Dewey, S.M.; Greene, G.; Deslattes, R.; Ulbig, S.; Lieb, K.P.; Casten, R.F.; Krusche, B.; Cizewski, J.A.

    1990-01-01

    Measurements of lifetimes of excited states in nuclei yield crucial information for sensitive tests of nuclear models. Here a novel method will be discussed which involves the GRID (Gamma Ray Induced Doppler broadening) technique, in which Doppler broadening is observed in a transition from a nucleus recoiling from the emission of a previous gamma ray. As the recoil energy is extremely small, ultra-high energy resolving power has to be used. To date all such experiments have been carried out at ILL using the GAMS4 double flat crystal spectrometer which is operated in a NIST-ILL collaboration. The method can be used for all lifetimes below a few picoseconds. The wide range of applicability, together with the very exhaustive set of data often obtained, is an advantage with respect to many other methods. The characteristic features of GRID will be discussed using some selected examples. 21 refs., 8 figs

  18. The determination of nuclear charge distributions using a Bayesian maximum entropy method

    International Nuclear Information System (INIS)

    Macaulay, V.A.; Buck, B.

    1995-01-01

    We treat the inference of nuclear charge densities from measurements of elastic electron scattering cross sections. In order to get the most reliable information from expensively acquired, incomplete and noisy measurements, we use Bayesian probability theory. Very little prior information about the charge densities is assumed. We derive a prior probability distribution which is a generalization of a form used widely in image restoration based on the entropy of a physical density. From the posterior distribution of possible densities, we select the most probable one, and show how error bars can be evaluated. These have very reasonable properties, such as increasing without bound as hypotheses about finer scale structures are included in the hypothesis space. The methods are demonstrated by using data on the nuclei 4 He and 12 C. (orig.)

  19. Determination of trace concentration of uranium in soils by the nuclear track technique

    International Nuclear Information System (INIS)

    Islam, G.S.; Abdullah, M.N.A.

    1998-04-01

    Solid state nuclear track detector CR-39 has been used to estimate trace concentration of uranium in soil and sand samples from various places of Bangladesh. Uranium contents in soil samples have been found to vary from ∼3.79 to ∼8.63 ppm and in sand samples from ∼2.39 to ∼6.53 ppm. The mean concentration in soil and in sand samples were found to be ∼4.52 and ∼2.96 ppm respectively. The maximum uranium concentration in soil samples was observed in Sylhet while the uranium concentration of sand was found to be maximum in the sea beach of Cox's Bazar. The implication of results is briefly discussed in the paper. (author)

  20. Disarmament and control of nuclear weapons: Russian positions and their national and international determining factors

    International Nuclear Information System (INIS)

    Facon, Isabelle

    2009-01-01

    In a context where Russia seems to come back to some key principles which guided its international action since the end of Cold War, and relationships between Russia and the USA have been degraded since the US intervention in Iraq (2003), the author examines whether these new Russian postures also concern strategic disarmament, whether Russia is loosing its interest in traditional arrangements of strategic stability, and what are Moscow's priorities within the perspective of expiry of the START 1 Treaty. Thus, the author discusses the role of nuclear weapons in the Russian defence policy, outlines the paradoxes of Russian negotiation positions in the fields of disarmament and arms control, and highlights indirect approaches adopted by Russia on these issues

  1. Analytical determination of traced elements in concrete samples used in nuclear reactors of the European Community

    International Nuclear Information System (INIS)

    May, S.; Piccot, D.

    1984-01-01

    In reactor dismantling residual radioacting of concrete used, especially in biological shield can brought problems for treatment and disposal. Radioactivity of concrete from reactors can be forecasted if element content is known. Elements producing long life radionuclides are: chlorine, calcium nickel, cobalt, niobium, europium and samarium. Neutron activation analysis is used for determination of these elements whithout chemical separation for Ca, Co, Eu and Sm and with radiochemical separation for Cl, Ni and Nb. A lot of elements, less interesting are also determined by gamma spectrometry after irradiation. It was possible to determine 29 elements in 21 concrete samples from different European Community reactors

  2. Impact of operator on determining functional parameters of nuclear medicine procedures.

    Science.gov (United States)

    Mohammed, A M; Naddaf, S Y; Mahdi, F S; Al-Mutawa, Q I; Al-Dossary, H A; Elgazzar, A H

    2006-01-01

    The study was designed to assess the significance of the interoperator variability in the estimation of functional parameters for four nuclear medicine procedures. Three nuclear medicine technologists with varying years of experience processed the following randomly selected 20 cases with diverse functions of each study type: renography, renal cortical scans, myocardial perfusion gated single-photon emission computed tomography (MP-GSPECT) and gated blood pool ventriculography (GBPV). The technologists used the same standard processing routines and were blinded to the results of each other. The means of the values and the means of differences calculated case by case were statistically analyzed by one-way ANOVA. The values were further analyzed using Pearson correlation. The range of the mean values and standard deviation of relative renal function obtained by the three technologists were 50.65 +/- 3.9 to 50.92 +/- 4.4% for renography, 51.43 +/- 8.4 to 51.55 +/- 8.8% for renal cortical scans, 57.40 +/- 14.3 to 58.30 +/- 14.9% for left ventricular ejection fraction from MP-GSPECT and 54.80 +/- 12.8 to 55.10 +/- 13.1% for GBPV. The difference was not statistically significant, p > 0.9. The values showed a high correlation of more than 0.95. Calculated case by case, the mean of differences +/- SD was found to range from 0.42 +/- 0.36% in renal cortical scans to 1.35 +/- 0.87% in MP-GSPECT with a maximum difference of 4.00%. The difference was not statistically significant, p > 0.19. The estimated functional parameters were reproducible and operator independent as long as the standard processing instructions were followed. Copyright 2006 S. Karger AG, Basel.

  3. Determination of internationally controlled materials according to provisions of the law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1977-01-01

    According to the provisions of The Law, those stipulated as internationally controlled materials are nuclear source materials, nuclear fuel materials, moderating materials, reactors and facilities, transferred from such as the U.S.A., the U.K. and Canada on the agreements of peaceful uses of atomic energy, and nuclear fuel materials accruing therefrom. (Mori, K.)

  4. A new facility for the determination of critical heat flux in nuclear fuel assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Fortman, R A; Hadaller, G I; Hamilton, R C; Hayes, R C; Shin, K S; Stern, F [Stern Laboratories Inc., Hamilton, ON (Canada)

    1993-11-01

    A facility for the determination of critical heat flux in simulated reactor fuel assemblies has been constructed at Stern Laboratories for CANDU Owners` Group. This paper describes the facility and method of testing. 9 figs.

  5. Determination of vibration amplitudes and neutron-mechanical scale factors in the PWR nuclear power plant

    International Nuclear Information System (INIS)

    Kostic, Lj.; Heidemann, P.; Runkel, J.

    1997-01-01

    Displacements of vibrating reactor components which can not be measured by other means during normal reactor operation can be determined through the scale factors from the neutron spectra of signals measured by the standard in-core neutron instrumentation. Neutron-mechanical scale factors are determined for the vibrations of fuel assemblies and reactor pressure vessel/core barrel system using the signals of in-core neutron detectors and accelerometers. (author)

  6. Homogeneity and fissure determination in uranium bars with solid state nuclear track detectors

    Energy Technology Data Exchange (ETDEWEB)

    Castillo, F. (Universidad Nacional Autonoma de Mexico, Mexico City. Facultad de Ciencias); Gamboa, I.; Espinosa, G.; Tapia, A. (Universidad Nacional Autonoma de Mexico, Mexico City. Inst. de Fisica); Somogyi, G. (Magyar Tudomanyos Akademia, Debrecen. Atommag Kutato Intezete)

    1984-01-01

    A simple and efficient method for determining fissure and concentration inhomogeneity in uranium bars is the alpha-radiographic technique. In our present work uranium bars made by ININ (Mexico) were studied by using CR-39 track detectors. The space inhomogeneity in track density was measured by an optical densitometer. The presence of fissure is determined by a microfiche reader. Such a study takes only few hours and does not require sophisticated instrumentation.

  7. Nuclear fuel technology - Determination of the O/M ratio in MOX pellets - Gravimetric method

    International Nuclear Information System (INIS)

    2008-01-01

    This International Standard describes a method for determining the oxygen-to-metal (O/M) ratio in mixed uranium-plutonium oxide pellets. The (U,Pu)O 2 x sample is submitted to controlled oxidation-reduction under thermodynamic conditions designed to change the O/M ratio to a value of 2,000. The initial stoichiometric deviation, X, is determined from the sample mass difference before and after heat treatment

  8. Determination of spent nuclear fuel assembly multiplication with the differential die-away self-interrogation instrument

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, Alexis C. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States); Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States); Henzl, Vladimir; Menlove, Howard O.; Swinhoe, Martyn T.; Belian, Anthony P. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States); Flaska, Marek; Pozzi, Sara A. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States)

    2014-09-01

    We present a novel method for determining the multiplication of a spent nuclear fuel assembly with a Differential Die-Away Self-Interrogation (DDSI) instrument. The signal, which is primarily created by thermal neutrons, is measured with four {sup 3}He detector banks surrounding a spent fuel assembly. The Rossi-alpha distribution (RAD) at early times reflects coincident events from single fissions as well as fission chains. Because of this fact, the early time domain contains information about both the fissile material and spontaneous fission material in the assembly being measured. A single exponential function fit to the early time domain of the RAD has a die-away time proportional to the spent fuel assembly (SFA) multiplication. This correlation was tested by simulating assay of 44 different SFAs with the DDSI instrument. The SFA multiplication was determined with a variance of 0.7%.

  9. Determination of maximum water temperature within the spent fuel pool of Angra Nuclear Power Plant - Unit 3

    Energy Technology Data Exchange (ETDEWEB)

    Werner, F.L., E-mail: fernanda.werner@poli.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Departamento de Engenharia Nuclear; Alves, A.S.M., E-mail: asergi@eletronuclear.gov.br [Eletrobras Termonuclear (Eletronuclear), Rio de Janeiro, RJ (Brazil); Frutuoso e Melo, P.F., E-mail: frutuoso@nuclear.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    In this paper, a mathematical model for the determination of the maximum water temperature within the spent fuel pool of Angra Nuclear Power Plant – Unit 3 was developed. The model was obtained from the boundary layer analysis and the application of Navier-Stokes equation to a vertical flat plate immersed in a water flow under free convection regime. Both types of pressure loss coefficients through the flow channel were considers in the modeling, the form coefficient for fuel assemblies (FAs) and the loss due to rod friction. The resulting equations enabled the determination of a mixed water temperature below the storage racks (High Density Storage Racks) as well as the estimation of a temperature gradient through the racks. The model was applied to the authorized operation of the plant (power operation, plant outage and upset condition) and faulted conditions (loss of coolant accidents and external events). The results obtained are in agreement with Brazilian and international standards. (author)

  10. Determination of maximum water temperature within the spent fuel pool of Angra Nuclear Power Plant - Unit 3

    International Nuclear Information System (INIS)

    Werner, F.L.; Frutuoso e Melo, P.F.

    2017-01-01

    In this paper, a mathematical model for the determination of the maximum water temperature within the spent fuel pool of Angra Nuclear Power Plant – Unit 3 was developed. The model was obtained from the boundary layer analysis and the application of Navier-Stokes equation to a vertical flat plate immersed in a water flow under free convection regime. Both types of pressure loss coefficients through the flow channel were considers in the modeling, the form coefficient for fuel assemblies (FAs) and the loss due to rod friction. The resulting equations enabled the determination of a mixed water temperature below the storage racks (High Density Storage Racks) as well as the estimation of a temperature gradient through the racks. The model was applied to the authorized operation of the plant (power operation, plant outage and upset condition) and faulted conditions (loss of coolant accidents and external events). The results obtained are in agreement with Brazilian and international standards. (author)

  11. Determination of aromatic fragment content in phenol-containing fractions of solid fuel conversion products using nuclear magnetic resonance spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Kanitskaya, L.V.; Kushnarev, D.F.; Polonov, V.M.; Kalabin, G.A.

    1986-03-01

    Optimum conditions are determined for obtaining quantitative nuclear magnetic resonance /sup 13/C spectra of fragments in phenol-containing fraction of coal products. Causes are analyzed of residual signals in spectra of un-protonized carbon atoms. The tests were carried out on: low-temperature carbonization tar and phenol fraction obtained during medium-temperature coking of Cherenkhovskii coal (which contains 84.13% C; 9.68% H; 1.23% S; 4.96% O); products of tar hydrogenation with various phenol content; standard phenol mixture. It was found that quantitative determination of aromatic fraction content in coal conversion products and other phenol- and amine-containing complex mixtures, using NMR spectroscopy requires the addition of dimethylsulfide or acetone in order to suppress specific interactions of phenols (amines) with relaxants and obtain quantitative subspectra of Tertiary and Quaternary aromatic carbon atoms. 16 references.

  12. Determination of {sup 241}Pu in nuclear waste slurries: A comparative study using LSC and ICP-MS

    Energy Technology Data Exchange (ETDEWEB)

    Jaeggi, M., E-mail: maya.jaeggi@psi.ch [Department Logistics for Radiation Safety and Security, Radioanalytics, CH-5232 Villligen PSI (Switzerland); Roellin, S., E-mail: Stefan.Roellin@babs.admin.ch [Federal Office for Civil Protection, SPIEZ Laboratory, CH-3700 Spiez (Switzerland); Corcho Alvarado, J.A., E-mail: Corcho-Alvarado@chuv.ch [Institute of Radiation Physics, University Hospital and University of Lausanne, Rue du Grand-Pre 1, 1007 Lausanne (Switzerland); Eikenberg, J., E-mail: jost.eikenberg@psi.ch [Department Logistics for Radiation Safety and Security, Radioanalytics, CH-5232 Villligen PSI (Switzerland)

    2012-02-15

    {sup 241}Pu was determined in slurry samples from a nuclear reactor decommissioning project at the Paul Scherrer Institute (Switzerland). To validate the results, the {sup 241}Pu activities of five samples were determined by LSC (TriCarb and Quantulus) and ICP-MS, with each instrument at a different laboratory. In lack of certified reference materials for {sup 241}Pu, the methods were further validated using the {sup 241}Pu information values of two reference sediments (IAEA-300 and IAEA-384). Excellent agreement with the results was found between LSC and ICP-MS in the nuclear waste slurries and the reference sediments. - Highlights: Black-Right-Pointing-Pointer Good agreement between the {sup 241}Pu activity of 5 slurry samples, using 3 measurement techniques. Black-Right-Pointing-Pointer {sup 241}Pu information values of two IAEA samples agreed well for the 3 measurement techniques. Black-Right-Pointing-Pointer Low detection limits were achieved; 1.8 Bq/kg (Quantulus), 2 Bq/kg (ICP-MS) and 3.5 Bq/kg (TriCarb).

  13. Determination of the Optimized Automation Rate considering Effects of Automation on Human Operators in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Seung Min; Seong, Poong Hyun; Kim, Jong Hyun; Kim, Man Cheol

    2015-01-01

    Automation refers to the use of a device or a system to perform a function previously performed by a human operator. It is introduced to reduce the human errors and to enhance the performance in various industrial fields, including the nuclear industry. However, these positive effects are not always achieved in complex systems such as nuclear power plants (NPPs). An excessive introduction of automation can generate new roles for human operators and change activities in unexpected ways. As more automation systems are accepted, the ability of human operators to detect automation failures and resume manual control is diminished. This disadvantage of automation is called the Out-of-the- Loop (OOTL) problem. We should consider the positive and negative effects of automation at the same time to determine the appropriate level of the introduction of automation. Thus, in this paper, we suggest an estimation method to consider the positive and negative effects of automation at the same time to determine the appropriate introduction of automation. This concept is limited in that it does not consider the effects of automation on human operators. Thus, a new estimation method for automation rate was suggested to overcome this problem

  14. Methodologies to determine the Pu content of spent fuel assemblies for input nuclear material accountancy of pyroporcessing

    International Nuclear Information System (INIS)

    Lee, Taehoon; Shin, Heesung; Kim, Youngsoo; Kim, Hodong; Kwon, Taeje

    2011-01-01

    This study shows two different non-destructive approaches to determine the Pu mass of spent fuel assemblies, and the analysis results on the errors in their Pu mass. For both methods, the Cm mass of the assembly is obtained based on the neutron measurement results. The Cm ratio of the assembly is determined from the Cm mass and the Pu mass obtained by using either of the two methods. In a comparison of two methods, the second method is simpler than the first and may not need a homogeneously-mixed sample of the spent fuel assembly. On the other hand, the second approach shows larger error in the estimated Pu mass than the first one for many different spent fuel cases of various burnup, initial enrichment, and cooling times. A member state support program for the development of the IAEA safeguards approach for an engineering-scale pyroprocessing facility, which is designated as the Reference Engineering-scale Pyroprocessing Facility(REPF), has been carried out by Korea Atomic Energy Research Institute since 2008. The nuclear material accountancy of the REPF is based on the 'Cm balance' technique. The Pu content of processing materials of pyroprocessing can be determined by measuring the Cm mass of the materials and multiplying it by the Cm ratio. The spent fuel assembly is de-cladded, and the irradiated UO 2 material of the assembly is homogeneously mixed in the homogenization process in order to obtain a representative sample of the spent fuel assembly for determining the mass of Pu, U and Cm elements, as well as the Cm ratio of the campaign. The shipper-receiver difference between the nuclear power plant and HPC of REPF is determined at this point. We found that the error for the Pu mass and Cm ratio determined from the homogenized uranium oxide powder is the most critical for the determination of the material unaccounted for throughout the whole processes. This paper presents two approaches to determine the Pu mass of spent fuel assemblies using non

  15. Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1976--September 30, 1977

    International Nuclear Information System (INIS)

    Waterbury, G.R.

    1978-01-01

    Development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for plutonium and uranium determinations, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, preparation of certified reference material plutonium metal, measurement of longer plutonium isotope half-lives, and study of ion exchange behavior of elements in various media continued. Gas-solid reaction of carbonyl chloride with uranium-bearing materials at elevated temperature is superior to reaction with chlorine for uranium volatilization and separation. Neither reaction with a variety of nonaqueous solvents nor reaction with molten selenium oxide provides practical dissolution of refractory materials characteristic of nuclear fuel cycle materials. The LASL automated spectrophotometer has been used to determine 0.1-mg amounts without instrumental or procedural changes. A microgram-sensitive spectrophotometric method for uranium has been developed, and the automated spectrophotometer is being modified to its use. A controlled-potential coulometric method has been developed for selective determination of plutonium. An automated analyzer to use this method is being built. Uranium-plutonium mixed oxide powder, for SALE samples, has not remained stable during storage, but high-density pellets have. In a DOE interlaboratory program, the half-life of 239 Pu has been measured, experiments on 241 Pu half-life measurement are in progress, and 240 Pu half-life measurement is planned. Ion exchange distributions for over 50 elements have been measured to determine cation exchange in nitric acid and anion exchange in both hydrobromic and hydriodic acids

  16. Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1976--September 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Waterbury, G.R. (comp.)

    1978-01-01

    Development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for plutonium and uranium determinations, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, preparation of certified reference material plutonium metal, measurement of longer plutonium isotope half-lives, and study of ion exchange behavior of elements in various media continued. Gas-solid reaction of carbonyl chloride with uranium-bearing materials at elevated temperature is superior to reaction with chlorine for uranium volatilization and separation. Neither reaction with a variety of nonaqueous solvents nor reaction with molten selenium oxide provides practical dissolution of refractory materials characteristic of nuclear fuel cycle materials. The LASL automated spectrophotometer has been used to determine 0.1-mg amounts without instrumental or procedural changes. A microgram-sensitive spectrophotometric method for uranium has been developed, and the automated spectrophotometer is being modified to its use. A controlled-potential coulometric method has been developed for selective determination of plutonium. An automated analyzer to use this method is being built. Uranium-plutonium mixed oxide powder, for SALE samples, has not remained stable during storage, but high-density pellets have. In a DOE interlaboratory program, the half-life of /sup 239/Pu has been measured, experiments on /sup 241/Pu half-life measurement are in progress, and /sup 240/Pu half-life measurement is planned. Ion exchange distributions for over 50 elements have been measured to determine cation exchange in nitric acid and anion exchange in both hydrobromic and hydriodic acids.

  17. Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1977--September 30, 1978

    International Nuclear Information System (INIS)

    Waterbury, G.R.

    1979-01-01

    Work has continued on the development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for plutonium and uranium determinations, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, preparation of plutonium materials for distribution by the National Bureau of Standards (NBS) as standard reference materials (SRMs), measurement of longer plutonium isotope half-lives, and analysis of SALE uranium materials. New tasks include the development of methods and automated instruments for the determination of thorium and uranium, and an evaluation of the ion-exchange-bead technique for the mass spectrometric measurement of uranium and plutonium isotope distributions. Completed tasks include the measurements of ion exchange distributions of over 50 elements on cation exchange resins from nitric acid media and anion exchange resins from hydrobromic and hydriodic acid media. Using a newly developed procedure, the LASL automated spectrophotometer was modified to determine microgram levels of uranium and to determine milligram levels of uranium and plutonium. Construction of an automated controlled-potential analyzer for the determination of plutonium is nearing completion. Apparatus and procedures for the separation and complexometric titration of thorium and uranium are being developed

  18. Determination of boron in nuclear materials at subppm levels by high pressure liquid chromatography (HPLC)

    International Nuclear Information System (INIS)

    Rao, Radhika M.; Aggarwal, S.K.

    2002-11-01

    Experiments were conducted for the determination of boron in U 3 O 8 powder, aluminium metal and milliQ water using dynamically modified Reversed Phase High Pressure Liquid Chromatography (RP-HPLC) and using two precolumn chromogenic agents viz. chromotropic acid and curcumin for complexing boron. The complex was separated from the excess of reagent and determined by HPLC. When present in subppm levels, chromotropic acid was used successfully only for determination boron in water samples. For determination of boron at subppm levels in uranium and aluminium samples, curcumin was used as the precolumn chromogenic agent. The boron curcumin complex (rosocyanin) was formed after extraction of boron with 2-ethyl-l, 3-hexane diol (EHD). The rosocyanin complex was then separated from excess curcumin by displacement chromatography. Linear calibration curves for boron amounts in the range of 0.02 μg to 0.5 μg were developed with correlation coefficients varying from 0.997 to 0.999 and were used for the determination of boron in aluminium and uranium samples. Precision of about 10% was achieved in samples containing less than 1 ppmw of boron. Detection limit of this method is 0.01 μg boron. (author)

  19. 70-kDa Heat Shock Cognate Protein hsc70 Mediates Calmodulin-dependent Nuclear Import of the Sex-determining Factor SRY*

    Science.gov (United States)

    Kaur, Gurpreet; Lieu, Kim G.; Jans, David A.

    2013-01-01

    We recently showed that the developmentally important family of SOX (SRY (sex determining region on the Y chromosome)-related high mobility group (HMG) box) proteins require the calcium-binding protein calmodulin (CaM) for optimal nuclear accumulation, with clinical mutations in SRY that specifically impair nuclear accumulation via this pathway resulting in XY sex reversal. However, the mechanism by which CaM facilitates nuclear accumulation is unknown. Here, we show, for the first time, that the 70-kDa heat shock cognate protein hsc70 plays a key role in CaM-dependent nuclear import of SRY. Using a reconstituted nuclear import assay, we show that antibodies to hsc70 significantly reduce nuclear accumulation of wild type SRY and mutant derivatives thereof that retain CaM-dependent nuclear import, with an increased rate of nuclear accumulation upon addition of both CaM and hsc70, in contrast to an SRY mutant derivative with impaired CaM binding. siRNA knockdown of hsc70 in intact cells showed similar results, indicating clear dependence upon hsc70 for CaM-dependent nuclear import. Analysis using the technique of fluorescence recovery after photobleaching indicated that hsc70 is required for the maximal rate of SRY nuclear import in living cells but has no impact upon SRY nuclear retention/nuclear dynamics. Finally, we demonstrate direct binding of hsc70 to the SRY·CaM complex, with immunoprecipitation experiments from cell extracts showing association of hsc70 with wild type SRY, but not with a mutant derivative with impaired CaM binding, dependent on Ca2+. Our novel findings strongly implicate hsc70 in CaM-dependent nuclear import of SRY. PMID:23235156

  20. Determination of fast neutron flux distribution in irradiation sites of the Malaysian Nuclear Agency research reactor

    International Nuclear Information System (INIS)

    Yavar, A.R.; Sarmani, S.B.; Wood, A.K.; Fadzil, S.M.; Radir, M.H.; Khoo, K.S.

    2011-01-01

    Determination of thermal to fast neutron flux ratio (f fast ) and fast neutron flux (φ fast ) is required for fast neutron reactions, fast neutron activation analysis, and for correcting interference reactions. The f fast and subsequently φ fast were determined using the absolute method. The f fast ranged from 48 to 155, and the φ fast was found in the range 1.03x10 10 -4.89x10 10 n cm -2 s -1 . These values indicate an acceptable conformity and applicable for installation of the fast neutron facility at the MNA research reactor.

  1. Local area distribution of fallout radionuclides from Fukushima Daiichi Nuclear Power Plant determined by autoradiography analysis

    International Nuclear Information System (INIS)

    Sakamoto, Fuminori; Ohnuki, Toshihiko; Kozai, Naofumi; Igarashi, Shosuke; Yamasaki, Shinya; Yoshida, Zenko; Tanaka, Shunichi

    2012-01-01

    The environmental behavior of radioactive Cs in the fallout from the accident of the Fukushima Daiichi Nuclear Power Plant has been studied by measuring its spatial distribution on/in trees, plants, and surface soil beneath the plants using autoradiography analysis. The results of autoradiography analysis showed that radioactive Cs was distributed on the branches and leaves of trees that were present during the accident and that only a small fraction of radioactive Cs was transported to new branches and leaves grown after the accident. Radioactive Cs was present on the grass and rice stubble on the soils, but not in the soils beneath the grass and rice stubble, indicating that the radioactive Cs was deposited on the grass and the rice plant. In addition, the ratio of the radioactive Cs that penetrated into the soil layer by weathering was very small two months after the accident. These results indicate that trees and other plants are the reservoir of the fallout Cs and function to retard the fallout Cs migration with rain water. (author)

  2. Determination of origin and intended use of plutonium metal using nuclear forensic techniques.

    Science.gov (United States)

    Rim, Jung H; Kuhn, Kevin J; Tandon, Lav; Xu, Ning; Porterfield, Donivan R; Worley, Christopher G; Thomas, Mariam R; Spencer, Khalil J; Stanley, Floyd E; Lujan, Elmer J; Garduno, Katherine; Trellue, Holly R

    2017-04-01

    Nuclear forensics techniques, including micro-XRF, gamma spectrometry, trace elemental analysis and isotopic/chronometric characterization were used to interrogate two, potentially related plutonium metal foils. These samples were submitted for analysis with only limited production information, and a comprehensive suite of forensic analyses were performed. Resulting analytical data was paired with available reactor model and historical information to provide insight into the materials' properties, origins, and likely intended uses. Both were super-grade plutonium, containing less than 3% 240 Pu, and age-dating suggested that most recent chemical purification occurred in 1948 and 1955 for the respective metals. Additional consideration of reactor modeling feedback and trace elemental observables indicate plausible U.S. reactor origin associated with the Hanford site production efforts. Based on this investigation, the most likely intended use for these plutonium foils was 239 Pu fission foil targets for physics experiments, such as cross-section measurements, etc. Copyright © 2017 Elsevier B.V. All rights reserved.

  3. [Nuclear protein matrix from giant nuclei of Chironomus plumosus determinates polythene chromosome organization].

    Science.gov (United States)

    Makarov, M S; Chentsov, Iu S

    2010-01-01

    Giant nuclei from salivary glands of Chironomus plumosus were treated in situ with detergent, 2 M NaCl and nucleases in order to reveal residual nuclear matrix proteins (NMP). It was shown, that preceding stabilization of non-histone proteins with 2 mM CuCl2 allowed to visualize the structure of polythene chromosomes at every stage of the extraction of histones and DNA. Stabilized NPM of polythene chromosomes maintains their morphology and banding patterns, which is observed by light and electron microscopy, whereas internal fibril net or residual nucleoli are not found. In stabilized NPM of polythene chromosomes, topoisomerase IIalpha and SMC1 retain their localization that is typical of untreated chromosomes. NPM of polythene chromosomes also includes sites of DNA replication, visualized with BrDU incubation, and some RNA-components. So, we can conclude that structure of NPM from giant nuclei is equal to NPM from normal interphase nuclei, and that morphological features of polythene chromosomes depend on the presence of NMP.

  4. Development of An Optimization Method for Determining Automation Rate in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Seung Min; Seong, Poong Hyun; Kim, Jong Hyun

    2014-01-01

    Since automation was introduced in various industrial fields, it has been known that automation provides positive effects like greater efficiency and fewer human errors, and negative effect defined as out-of-the-loop (OOTL). Thus, before introducing automation in nuclear field, the estimation of the positive and negative effects of automation on human operators should be conducted. In this paper, by focusing on CPS, the optimization method to find an appropriate proportion of automation is suggested by integrating the suggested cognitive automation rate and the concepts of the level of ostracism. The cognitive automation rate estimation method was suggested to express the reduced amount of human cognitive loads, and the level of ostracism was suggested to express the difficulty in obtaining information from the automation system and increased uncertainty of human operators' diagnosis. The maximized proportion of automation that maintains the high level of attention for monitoring the situation is derived by an experiment, and the automation rate is estimated by the suggested automation rate estimation method. It is expected to derive an appropriate inclusion proportion of the automation system avoiding the OOTL problem and having maximum efficacy at the same time

  5. Determining Bond Sodium Remaining in Plenum Region of Spent Nuclear Driver Fuel

    International Nuclear Information System (INIS)

    Vaden, D.; Li, S.X.

    2008-01-01

    The Fuel Conditioning Facility (FCF) at the Idaho National Laboratory (INL) treats spent nuclear fuel using an electro-chemical process that separates the uranium from the fission products, sodium thermal bond, and cladding materials (REF 1). Upon immersion into the ER electrolyte, the sodium used to thermally bond the fuel to the clad jacket chemically reacts with the UCl3 in the electrolyte producing NaCl and uranium metal. The uranium in the spent fuel is separated from the cladding and fission products by taking advantage of the electro-chemical potential differences between uranium and the other fuel components. Assuming all the sodium in the thermal bond is converted to NaCl in the ER, the difference between the cumulative bond sodium mass in the fuel elements and the cumulative sodium mass found in the driver ER electrolyte inventory provides an upper mass limit for the sodium that migrated to the upper gas region, or plenum section, of the fuel element during irradiation in the reactor. The plenums are to be processed as metal waste via melting and metal consolidation operations. However, depending on the amount of sodium in the plenums, additional processing may be required to remove the sodium before metal waste processing

  6. Determination of nuclear friction in strongly damped reactions from prescission neutron multiplicities

    International Nuclear Information System (INIS)

    Wilczynski, J.; Siwek-Wilczynska, K.; Wilschut, H.W.

    1996-01-01

    Nonfusion, fissionlike reactions in collisions of four heavy systems (well below the fusion extra-push energy threshold), for which Hinde and co-workers had measured the prescission neutron multiplicities, have been analyzed in terms of the deterministic dynamic model of Feldmeier coupled to a time-dependent statistical cascade calculation. In order to reproduce the measured prescission multiplicities and the observed (nearly symmetric) mass divisions, the energy dissipation must be dramatically changed with regard to the standard one-body dissipation: In the entrance channel, in the process of forming a composite system, the energy dissipation has to be reduced to at least half of the one-body dissipation strength (k s in ≤0.5), and in the exit channel (from a mononucleus shape to scission) it must be increased by a factor ranging for the studied reactions from k s out =4 to k s out =12. These results are compared with the temperature dependence of the friction coefficient, recently deduced by Hofman, Back, and Paul from data on the prescission giant dipole resonance emission in fusion-fission reactions. The combined picture of the temperature dependence of the friction coefficient, for both fusion-fission and nonfusion reactions, may indicate the onset of strong two-body dissipation already at a nuclear temperature of about 2 MeV. copyright 1996 The American Physical Society

  7. RAPID AUTOMATED RADIOCHEMICAL ANALYZER FOR DETERMINATION OF TARGETED RADIONUCLIDES IN NUCLEAR PROCESS STREAMS

    International Nuclear Information System (INIS)

    O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Egorov, Oleg; Devol, Timothy A.

    2008-01-01

    Some industrial process-scale plants require the monitoring of specific radionuclides as an indication of the composition of their feed streams or as indicators of plant performance. In this process environment, radiochemical measurements must be fast, accurate, and reliable. Manual sampling, sample preparation, and analysis of process fluids are highly precise and accurate, but tend to be expensive and slow. Scientists at Pacific Northwest National Laboratory (PNNL) have assembled and characterized a fully automated prototype Process Monitor instrument which was originally designed to rapidly measure Tc-99 in the effluent streams of the Waste Treatment Plant at Hanford, WA. The system is capable of a variety of tasks: extraction of a precise volume of sample, sample digestion/analyte redox adjustment, column-based chemical separations, flow-through radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results can be immediately calculated and electronically reported. It is capable of performing a complete analytical cycle in less than 15 minutes. The system is highly modular and can be adapted to a variety of sample types and analytical requirements. It exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

  8. Nuclear reprogramming: kinetics of cell cycle and metabolic progression as determinants of success.

    Directory of Open Access Journals (Sweden)

    Sebastian Thomas Balbach

    Full Text Available Establishment of totipotency after somatic cell nuclear transfer (NT requires not only reprogramming of gene expression, but also conversion of the cell cycle from quiescence to the precisely timed sequence of embryonic cleavage. Inadequate adaptation of the somatic nucleus to the embryonic cell cycle regime may lay the foundation for NT embryo failure and their reported lower cell counts. We combined bright field and fluorescence imaging of histone H(2b-GFP expressing mouse embryos, to record cell divisions up to the blastocyst stage. This allowed us to quantitatively analyze cleavage kinetics of cloned embryos and revealed an extended and inconstant duration of the second and third cell cycles compared to fertilized controls generated by intracytoplasmic sperm injection (ICSI. Compared to fertilized embryos, slow and fast cleaving NT embryos presented similar rates of errors in M phase, but were considerably less tolerant to mitotic errors and underwent cleavage arrest. Although NT embryos vary substantially in their speed of cell cycle progression, transcriptome analysis did not detect systematic differences between fast and slow NT embryos. Profiling of amino acid turnover during pre-implantation development revealed that NT embryos consume lower amounts of amino acids, in particular arginine, than fertilized embryos until morula stage. An increased arginine supplementation enhanced development to blastocyst and increased embryo cell numbers. We conclude that a cell cycle delay, which is independent of pluripotency marker reactivation, and metabolic restraints reduce cell counts of NT embryos and impede their development.

  9. Determination of the radioiodine species in the exhaust air of nuclear facilities

    International Nuclear Information System (INIS)

    Birke, G.; Deuber, H.

    1977-01-01

    In the stack exhaust air of the nuclear power stations the portion of inorganic 131 I was, apart from 2 sampling periods, less than 50%. In the stack exhaust air of the research reactor the inorganic 131 I prevailed. The removal efficiency of the I 2 sorption materials DSM 11 and DSM 17 for 131 I in the form of CH 3 I and C 6 H 5 I was very low. 131 I in the form of C 6 H 5 I was removed by AC 6120 and LMS 13 X-Ag (Linde molecular sieve in the Ag form) to a very small extent too, by activated charcoal impregnated with KI or TEDA however to a very high extent. In the experiments concerning the preparation and removal of 131 I in the form of HIO an iodine species that was difficult to remove with AC 6120 was found which could be HIO. Its maximum portion in the carrier gas was 50%. (orig./RW) [de

  10. Continuous parameter determination of irradiated nuclear fuels in the test-reactor

    International Nuclear Information System (INIS)

    Bevilacqua, A.; Junod, E.; Mas, P.; Perdreau, R.

    1977-01-01

    During the irradiation tests of nuclear fuels, the flux level may often be variable by shifting the loops in a high neutron-gradient. So integral fluence measurements are no longer sufficient. The self-powered neutron detectors allow to finely scan instantaneous fluxes. More than 100 such SPN detectors are used on the experiments irradiated in the SILOE reactor. The treatment of the large amount of information is following. A first minicomputer scans all the measurement lines at a variable frequence (10 min to 1 hr) and writes rough voltage values on a magnetic disk. A second computer does a sorting of these values for each set of SPND corresponding to an experiment. At the present time, the main treatment is performed by batch processing by some FORTRAN codes to get time-evolving quantities, such as effective flux, fission power, burn-up, fission product activities, etc. The future development of the system will allow some of these calculations to be performed directly on the second computer in such a manner to control the movements of the loops automatically in view of a given irradiation program

  11. Thermal Lens Spectroscopy as a 'new' analytical tool for actinide determination in nuclear reprocessing processes

    International Nuclear Information System (INIS)

    Canto, Fabrice; Couston, Laurent; Magnaldo, Alastair; Broquin, Jean-Emmanuel; Signoret, Philippe

    2008-01-01

    Thermal Lens Spectroscopy (TLS) consists of measuring the effects induced by the relaxation of molecules excited by photons. Twenty years ago, the Cea already worked on TLS. Technologic reasons impeded. But, needs in sensitive analytical methods coupled with very low sample volumes (for example, traces of Np in the COEX TM process) and also the reduction of the nuclear wastes encourage us to revisit this method thanks to the improvement of optoelectronic technologies. We can also imagine coupling TLS with micro-fluidic technologies, decreasing significantly the experiments cost. Generally two laser beams are used for TLS: one for the selective excitation by molecular absorption (inducing the thermal lens) and one for probing the thermal lens. They can be coupled with different geometries, collinear or perpendicular, depending on the application and on the laser mode. Also, many possibilities of measurement have been studied to detect the thermal lens signal: interferometry, direct intensities variations, deflection etc... In this paper, one geometrical configuration and two measurements have been theoretically evaluated. For a single photodiode detection (z-scan) the limit of detection is calculated to be near 5*10 -6 mol*L -1 for Np(IV) in dodecane. (authors)

  12. One procedure for determination of the neutron flux in the nuclear reactor fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bulovic, V; Krtil, J; Maksimovic, Z; Martinc, R [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1979-09-15

    Possibility of determination of the neutron flux in the fuel of a heavy water reactor has been examined. In determination of the flux an iterative procedure was used to compare calculated and measured contents of several fission products. The former contents were determined by calculation of the burning process balance and the latter by non-destructive gamma-spectrometric analysis of fuel. The obtained results prove the possibility of such determination of not only the average value of the flux but also of the change of its intensity during utilization of fuel (author) U radu je ispitivana mogucnost odredjivanja fluksa neutrona u gorivu teskovodnog nuklearnog reaktora. Pri odredjivanju fluksa koriscen je iterativni postupak, u kome se porede izracunati i izmereni sadrzaji nekoliko gama-radioaktivnih fisionih produkata. Prvi sadrzaji su odredjivani preko proracuna bilansa procesa sagorevanja, a drugi - nedestruktivnom gama-spektrometrijskom analizom goriva. Dobijeni rezultati potvrdjuju mogucnost ovakvog odredjivanja ne samo srednje vrednosti fluksa, vec i promene njegovog intenziteta u toku koriscenja goriva (author)

  13. Automation of potentiometric titration for the determination of uranium in nuclear fuel materials

    International Nuclear Information System (INIS)

    Kelkar, Anoop; Pandey, Ashish; Kapoor, Y.S.; Kumar, Manish; Singh, Mamta; Fulzele, Ajeet; Prakash, Amrit; Afzal, Mohd; Panakkal, J.P.

    2010-01-01

    Advanced Fuel Fabrication Facility is fabricating various types of mixed oxide fuels, namely for PHWR, BWR, FBTR and PFBR. Precise determination of uranium in MOX fuel sample is important to get desired burn up in the reactor. The modified Davies and Gray method is routinely used for the potentiometric titration of uranium

  14. Feasibility of a novel approach for fast, economical determination of radiation damage in nuclear reactor cores

    International Nuclear Information System (INIS)

    Was, G.S.

    1993-01-01

    Progress was made in the following areas: radioinduced segregation (modeling and experiment), deformation of irradiated microstructures, stress corrosion cracking of irradiated microstructures, and development of an apparatus to determine the role of deformation on the radiation microstructure in-situ. Materials used were based on Ni-Cr-Fe and 304L

  15. Nuclear energy - Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets

    International Nuclear Information System (INIS)

    2008-01-01

    This International Standard describes a method for determining the chlorine and fluorine concentrations in uranium dioxide and in sintered fuel pellets by pyrohydrolysis of samples, followed either by liquid ion-exchange chromatography or by selective electrode measurement of chlorine and fluorine ions. Many ion-exchange chromatography systems and ion-selective electrode measurement systems are available

  16. ILK statement on determining operation periods for nuclear power plants in Germany

    International Nuclear Information System (INIS)

    2005-09-01

    The question of how long nuclear power plants (NPPs) can be safely operated while maintaining a high safety standard played an important role in the worldwide expert discussion in recent years. Far-reaching agreement exists on which reviews and measures to undertake in order to safely operate such plants over longer time periods. In most countries operating licenses for NPPs are not limited in time; this is also the case for Germany. However, the authorization for power operation expires if the plant has used up its approved electricity generation quota. This quota corresponds to a value established in the Atomic Energy Act (AtG) for the individual unit that is based on an operating time of 32 years. On the basis of operating experiences gathered with plants currently in operation and also due to available research findings, the ILK believes that there are no safetyrelated reasons for limiting the operating time of nuclear power plants a priori. The ILK notes that the German NPPs have a high safety standard that is constantly monitored by the regulatory authority. Periodic safety reviews (PSRs), which are performed every ten years, are part of this process. The ILK also takes the view, however, that in the case of very long operating periods, it makes sense to make the continued operation depend on a renewed evaluation (of the plant). This requires demonstrating that the plant displays a level of safety that corresponds to the requirements for the future operating period. The ILK recommends the following approach: - The limitation of production quotas currently laid down in the German Atomic Energy Act should be lifted; - In addition to maintaining the current safety standard, licensees should examine improvement measures for the further reduction of the residual risk and, where appropriate, apply these. The effectiveness of the PSR in its current form should be assessed and the guidelines for their application should be updated, if necessary; - After an operating

  17. Standard test method for determination of impurities in nuclear grade uranium compounds by inductively coupled plasma mass spectrometry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This test method covers the determination of 67 elements in uranium dioxide samples and nuclear grade uranium compounds and solutions without matrix separation by inductively coupled plasma mass spectrometry (ICP-MS). The elements are listed in Table 1. These elements can also be determined in uranyl nitrate hexahydrate (UNH), uranium hexafluoride (UF6), triuranium octoxide (U3O8) and uranium trioxide (UO3) if these compounds are treated and converted to the same uranium concentration solution. 1.2 The elements boron, sodium, silicon, phosphorus, potassium, calcium and iron can be determined using different techniques. The analyst's instrumentation will determine which procedure is chosen for the analysis. 1.3 The test method for technetium-99 is given in Annex A1. 1.4 The values stated in SI units are to be regarded as standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish ...

  18. Experimental determination of nuclear reaction rates (n,γ) by the gamma-rays capture spectrometry technique

    International Nuclear Information System (INIS)

    Lucatero, M.A.

    1976-01-01

    The technique of the gamma-rays capture spectrometry was used in the experimental determination of nuclear reaction rates of the type (n,γ). This technique consists in the incidence of a thermal neutrons collimated beam upon a sample, detecting the capture spectrum of gamma rays emitted at a solid fixed angle. In the determination of the efficiency curve intrinsic to the detection electronic system the reactions 199 Hg(n,γ) 200 Hg, 56 Fe(n,γ) 57 Fe and 63 Cu(n,γ) 64 Cu were used with the energy of the gamma rays capture of 5.976, 7.635 and 7.915 Mev respectively, through the irradiation of standard samples of Hg(175.3g), Fe(110.4g) and Cu(108.5g) of cylindrical geometry the two former and parallelepiped the latter. The problem concerning the corrections due to the thermal neutrons flux depression, the gammas auto-attenuation, and the geometric factor due to the cylindrical and parallelepiped geometry are involved in the data process. The experimental determination of the reaction 35 Cl(n,γ) 36 Cl rate was made through the observation of the gamma caputre of 6.111 Mev when a sample of CaCl 2 of cylindrical geometry was irradiated. This rate can be favorably compared with the reaction rate determined theoretically. (author)

  19. Validation of a residue method to determine pesticide residues in cucumber by using nuclear techniques

    International Nuclear Information System (INIS)

    Baysoyu, D.; Tiryaki, O.; Secer, E.; Aydin, G.

    2009-01-01

    In this study, a multi-residue method using ethyl acetate for extraction and gel permeation chromatography for clean-up was validated to determine chlorpyrifos, malathion and dichlorvos in cucumber by gas chromatography. For this purpose, homogenized cucumber samples were fortified with pesticides at 0.02 0.2, 0.8 and 1 mg/kg levels. The efficiency and repeatability of the method in extraction and cleanup steps were performed using 1 4C-carbaryl by radioisotope tracer technique. 1 4C-carbaryl recoveries after the extraction and cleanup steps were between 92.63-111.73 % with a repeatability of 4.85% (CV) and 74.83-102.22 % with a repeatability of 7.19% (CV), respectively. The homogeneity of analytical samples and the stability of pesticides during homogenization were determined using radio tracer technique and chromatographic methods, respectively.

  20. Direct determination by atomic absorption of calcium, cobalt and zinc in nuclear grade uranium oxide

    International Nuclear Information System (INIS)

    Guido, O.O.; Amaya, Carlos.

    1975-05-01

    A study has been made of the effect of flame composition (fuel: C 2 H 2 , comburent: air or N 2 O) and location of the burner on the three analytes in a nitric medium, in presence and in absence of uranium. For calcium it was necessary to use N 2 O, while for zinc and cobalt the use of air was found more adequate. The standard additions method for the quantitative determination was adopted. The absorption at the analytical wavelength not corresponding to the elements studied was determined by comparison between this method and another indirect one, using extraction with TBP, and the results were expressed as equivalent concentrations. Confidence intervals of the analytical results were evaluated statistically using a scheme of calculation adapted to the proposed method. This evaluation allowed an estimation of the detection limits (calcium: 5 ppm, cobalt: 3 ppm, zinc: 1 ppm). (author)

  1. Spectrographic determination of impurities in ceramic materials for nuclear fusion reactors III. Analysis of magnesium oxide

    International Nuclear Information System (INIS)

    Melon, A. M.; Roca, M.; Rucandio, M. I.

    1992-01-01

    The determination of minor and trace elements in the magnesium oxide, considered as possible ceramic material in thermonuclear fusion reactors, has been studied. The concentration ranges are 0.1 - 0.3% for Ca, Si and Y, and at the ppm level for Al, Co, Cr, Fe, Hf, K, Li, Mn, Na, Ni, Se, Ti, V and Zr. Atomic emission spectroscopy with direct current are excitation and photographic detection has been employed. In order to eliminate the effect due to the differences in density between standards and samples, which are a source of errors, a chemical treatment of both is carried out. Likewise, for attaining conditions more suitable for the volatilization of certain impurities, these are determined with the sample in fluoride form. (Author) 11 refs

  2. Spectrographic determination of impurities in ceramic materials for nuclear fusion reactors III. Analysis of magnesium oxide

    International Nuclear Information System (INIS)

    Melon, A.M.; Roca, M.; Rucandio, M.I.

    1992-01-01

    The determination of minor and trace elements in the magnesium oxide, considered as possible ceramic material in thermonuclear fusion reactors, has been studied. The concentration ranges are 0.1 - 0.3 % for Ca, Si and Y, and at the ppm level for Al, Co, Cr, Fe, Hf, K, Li, Mn, Na, Ni, Sc, Ti, V and Zr. Atomic emission spectroscopy with direct current arc excitation and photographic detection has been employed. In order to eliminated the effect due to the differences in density between standards and samples, which are a source of errors, a chemical treatment of both is carried out. Likewise, for attaining conditions more suitable for the volatilization of certain impurities, these are determined with the sample in fluoride form. (author)

  3. Determination of the vibration characteristics of nuclear fuel rods in a fluid flow using multiphysics computation

    International Nuclear Information System (INIS)

    Sbragio, Ricardo

    1999-01-01

    The determination of natural frequencies and displacement Power Spectrum Density (PSD) of fuel rods in a fluid using Computational Fluid Dynamics and Finite Element Methods is presented. The rods are modeled as slender beams subjected to small displacements in a fluid using three-dimensional mesh. The incompressible Navier-Stokes and linear momentum balance equations are solved simultaneously using Spectrum code. Two examples from literature are analyzed. The first consists in one rod in a fluid. The excitation is an impulse force at the rod central node. The second example is a two rod system in a fluid. In this case, the excitation force is random and is determined from a PSD. (author)

  4. Reserve seismic capacity determination of a nuclear power plant braced frame with piping

    International Nuclear Information System (INIS)

    Nelson, T.A.

    1979-01-01

    A typical diagonal braced steel frame was developed to determine the amount of reserve capacity that is available beyond elastic design levels. The frame was analyzed first using elastic static and dynamic analyses. The loadings included dead and live load, an equivalent static lateral earthquake load, two response spectra and a suite of eight earthquake time history records. The response spectra used were the Housner and Regulatory Guide 1.60. The time histories represented different site conditions, distances to causative faults and magnitudes. The lateral static load and Housner spectrum represent vintage design criteria, while the R.G. 1.60 and time history analyses reflect current methodology. The elastic limit responses of the structure were determined along with the accompanying threshold peak ground accelerations (threshold g values). The frame was then analyzed using the program DRAIN-2D to perform two-dimensional elastic--plastic analyses for the eight time histories

  5. Simplified Model of Safety Determination Process for a Country with its First Operating Nuclear Power Plants

    International Nuclear Information System (INIS)

    Saud, Bin Khadim; Chung, Dae Wook

    2013-01-01

    The two inputs are evaluated and given a color designation based on their safety significance. The performance indicators (PIs) in ROP program were developed from a very large statistical basis given operating experience from 100 reactors over a long period of time. The inspection findings are evaluated in terms of changes in core damage frequency using simplified PRA models and in some cases more complex models. The aim of this paper is to develop a simplified risk assessment approach for inspection findings which does not use PRA directly, but may use direct calculation approach. Thus, it would be helpful for inspectors to determine the safety significance of inspection findings. The objective of this study was to develop a simplified risk assessment approach for inspection findings using direct risk calculation model to determine the safety significance. Risk and categorization scheme are developed to put inspection finding into corresponding ΔCDF category

  6. A new shape specimens determined the J1c value of nuclear pressure vessel steel

    International Nuclear Information System (INIS)

    Xu, W.Q.

    1989-01-01

    The J integral has two basic definitions, a two-dimensional energy line integral definition and an energy rate definition. The line integral definition cannot be used for this experimental determination. The energy rate definition can be used but the procedure is somewhat laborious. Methods were developed for more easily determining J by approximation formulas. The first of these were where J could be estimated with reasonable accuracy for a deeply cracked bend-type specimen. This method is slightly inaccurate. This paper is concerned with a new shape specimen. It is called the W-shape specimen. The W-shape specimens are smaller volume than the compact specimens. It is convenient to operate the W-shape specimens in hot cell. It can be put into surveillance capsules and can also do specimen irradiation in engineering test reactor

  7. Simplified Model of Safety Determination Process for a Country with its First Operating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Saud, Bin Khadim [Korea Advance Institute of Science and Technology, Daejeon (Korea, Republic of); Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    The two inputs are evaluated and given a color designation based on their safety significance. The performance indicators (PIs) in ROP program were developed from a very large statistical basis given operating experience from 100 reactors over a long period of time. The inspection findings are evaluated in terms of changes in core damage frequency using simplified PRA models and in some cases more complex models. The aim of this paper is to develop a simplified risk assessment approach for inspection findings which does not use PRA directly, but may use direct calculation approach. Thus, it would be helpful for inspectors to determine the safety significance of inspection findings. The objective of this study was to develop a simplified risk assessment approach for inspection findings using direct risk calculation model to determine the safety significance. Risk and categorization scheme are developed to put inspection finding into corresponding ΔCDF category.

  8. Determination of fast neutron flux distribution in irradiation sites of the Malaysian Nuclear Agency research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yavar, A.R. [School of Applied Physics, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia); Sarmani, S.B. [School of Chemical Sciences and Food Technology, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia); Wood, A.K. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, 43000 Kajang, Selangor (Malaysia); Fadzil, S.M. [School of Applied Physics, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia); Radir, M.H. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, 43000 Kajang, Selangor (Malaysia); Khoo, K.S., E-mail: khoo@ukm.m [School of Applied Physics, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia)

    2011-05-15

    Determination of thermal to fast neutron flux ratio (f{sub fast}) and fast neutron flux ({phi}{sub fast}) is required for fast neutron reactions, fast neutron activation analysis, and for correcting interference reactions. The f{sub fast} and subsequently {phi}{sub fast} were determined using the absolute method. The f{sub fast} ranged from 48 to 155, and the {phi}{sub fast} was found in the range 1.03x10{sup 10}-4.89x10{sup 10} n cm{sup -2} s{sup -1}. These values indicate an acceptable conformity and applicable for installation of the fast neutron facility at the MNA research reactor.

  9. Chromatin Structure and Replication Origins: Determinants Of Chromosome Replication And Nuclear Organization

    Science.gov (United States)

    Smith, Owen K.; Aladjem, Mirit I.

    2014-01-01

    The DNA replication program is, in part, determined by the epigenetic landscape that governs local chromosome architecture and directs chromosome duplication. Replication must coordinate with other biochemical processes occurring concomitantly on chromatin, such as transcription and remodeling, to insure accurate duplication of both genetic and epigenetic features and to preserve genomic stability. The importance of genome architecture and chromatin looping in coordinating cellular processes on chromatin is illustrated by two recent sets of discoveries. First, chromatin-associated proteins that are not part of the core replication machinery were shown to affect the timing of DNA replication. These chromatin-associated proteins could be working in concert, or perhaps in competition, with the transcriptional machinery and with chromatin modifiers to determine the spatial and temporal organization of replication initiation events. Second, epigenetic interactions are mediated by DNA sequences that determine chromosomal replication. In this review we summarize recent findings and current models linking spatial and temporal regulation of the replication program with epigenetic signaling. We discuss these issues in the context of the genome’s three-dimensional structure with an emphasis on events occurring during the initiation of DNA replication. PMID:24905010

  10. Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions

    Energy Technology Data Exchange (ETDEWEB)

    González-Robles, E., E-mail: ernesto.gonzalez-robles@kit.edu [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Metz, V. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Wegen, D.H. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Herm, M. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Papaioannou, D. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Bohnert, E. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Gretter, R. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Müller, N. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany); Nasyrow, R.; Weerd, W. de; Wiss, T. [European Commission, Joint Research Centre, Institute for Transuranium Elements (JRC-ITU), P.O. Box 2340, 76125, Karlsruhe (Germany); Kienzler, B. [Karlsruhe Institute of Technology, Institute for Nuclear Waste Disposal (KIT-INE), P.O. Box 3640, D-76021, Karlsruhe (Germany)

    2016-10-15

    During reactor operation the fission gases Kr and Xe are formed within the UO{sub 2} matrix of nuclear fuel. Their quantification is important to evaluate their impact on critical parameters regarding the fuel behaviour during irradiation and (long-term) interim storage, such as internal pressure of the fuel rod and fuel swelling. Moreover the content of Kr and Xe in the plenum of a fuel rod and their content in the UO{sub 2} fuel itself are widely used as indicators for the release properties of {sup 129}I, {sup 137}Cs, and other safety relevant radionuclides with respect to final disposal of spent nuclear fuel. The present study deals with the fission gas release from spent nuclear fuel exposed to simulated groundwater in comparison with the fission gas previously released to the fuel rod plenum during irradiation in reactor. In a unique approach we determined both the Kr and Xe inventories in the plenum by means of a puncturing test and in leaching experiments with a cladded fuel pellet and fuel fragments in bicarbonate water under 3.2 bar H{sub 2} overpressure. The fractional inventory of the fission gases released during irradiation into the plenum was (8.3 ± 0.9) %. The fraction of inventory of fission gases released during the leaching experiments was (17 ± 2) % after 333 days of leaching of the cladded pellet and (25 ± 2) % after 447 days of leaching of the fuel fragments, respectively. The relatively high release of fission gases in the experiment with fuel fragments was caused by the increased accessibility of water to the Kr and Xe occluded in the fuel.

  11. Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants – Interim Study FY13

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, Kevin L.; Fifield, Leonard S.; Westman, Matthew P.; Ramuhalli, Pradeep; Pardini, Allan F.; Tedeschi, Jonathan R.; Jones, Anthony M.

    2013-09-27

    The most important criterion for cable performance is its ability to withstand a design-basis accident. With nearly 1000 km of power, control, instrumentation, and other cables typically found in an NPP, it would be a significant undertaking to inspect all of the cables. Degradation of the cable jacket, electrical insulation, and other cable components is a key issue that is likely to affect the ability of the currently installed cables to operate safely and reliably for another 20 to 40 years beyond the initial operating life. The development of one or more nondestructive evaluation (NDE) techniques and supporting models that could assist in determining the remaining life expectancy of cables or their current degradation state would be of significant interest. The ability to nondestructively determine material and electrical properties of cable jackets and insulation without disturbing the cables or connections has been deemed essential. Currently, the only technique accepted by industry to measure cable elasticity (the gold standard for determining cable insulation degradation) is the indentation measurement. All other NDE techniques are used to find flaws in the cable and do not provide information to determine the current health or life expectancy. There is no single NDE technique that can satisfy all of the requirements needed for making a life-expectancy determination, but a wide range of methods have been evaluated for use in NPPs as part of a continuous evaluation program. The commonly used methods are indentation and visual inspection, but these are only suitable for easily accessible cables. Several NDE methodologies using electrical techniques are in use today for flaw detection but there are none that can predict the life of a cable. There are, however, several physical and chemical ptoperty changes in cable insulation as a result of thermal and radiation damage. In principle, these properties may be targets for advanced NDE methods to provide early

  12. Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants - Interim Study FY13

    International Nuclear Information System (INIS)

    Simmons, Kevin L.; Fifield, Leonard S.; Westman, Matthew P.; Ramuhalli, Pradeep; Pardini, Allan F.; Tedeschi, Jonathan R.; Jones, Anthony M.

    2013-01-01

    The most important criterion for cable performance is its ability to withstand a design-basis accident. With nearly 1000 km of power, control, instrumentation, and other cables typically found in an NPP, it would be a significant undertaking to inspect all of the cables. Degradation of the cable jacket, electrical insulation, and other cable components is a key issue that is likely to affect the ability of the currently installed cables to operate safely and reliably for another 20 to 40 years beyond the initial operating life. The development of one or more nondestructive evaluation (NDE) techniques and supporting models that could assist in determining the remaining life expectancy of cables or their current degradation state would be of significant interest. The ability to nondestructively determine material and electrical properties of cable jackets and insulation without disturbing the cables or connections has been deemed essential. Currently, the only technique accepted by industry to measure cable elasticity (the gold standard for determining cable insulation degradation) is the indentation measurement. All other NDE techniques are used to find flaws in the cable and do not provide information to determine the current health or life expectancy. There is no single NDE technique that can satisfy all of the requirements needed for making a life-expectancy determination, but a wide range of methods have been evaluated for use in NPPs as part of a continuous evaluation program. The commonly used methods are indentation and visual inspection, but these are only suitable for easily accessible cables. Several NDE methodologies using electrical techniques are in use today for flaw detection but there are none that can predict the life of a cable. There are, however, several physical and chemical ptoperty changes in cable insulation as a result of thermal and radiation damage. In principle, these properties may be targets for advanced NDE methods to provide early

  13. Nuclear parameters determination of the {sup 127}Te {beta} {sup -} decay: a proposal for teaching nuclear physics; Determinacao de parametros nucleares do nucleo de {sup 127}Te: uma proposta para o ensino de fisica nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Batista, Wagner Fonseca

    2011-07-01

    A study of the {sup 127}Te {beta}{sup -} decay was carried out by means of gamma spectroscopy measurements using high resolution HPGe detector, in the region from 30 keV to 1.0 MeV, aiming to get a better understanding of the {sup 127}Te nuclear structure. The radioactive sources of {sup 12}7Te were obtained from the {sup 126}Te(n,{gamma}){sup 1}'2{sup 7}Te nuclear reaction produced in the IEA- R1 nuclear reactor at IPEN/CNEN-SP. Five gamma {sup t}ransitions previously attributed to this decay were confirmed with a better precision than previously. The half-life of {sup 127}Te was also studied resulting in data with lower uncertainty. Using a set of data selected from gamma spectroscopy measurements was developed and applied a didactic proposal for high school students using the Excel software. (author)

  14. Determination of internationally controlled materials according to provisions of the law for the regulations of nuclear source materials, nuclear fuel materials and reactors

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and reactors, and the former notification No. 26, 1961, is hereby abolished. Internationally regulated goods under the law are as follows: nuclear raw materials, nuclear fuel materials and moderator materials transferred by sale or other means from the governments of the U.S., U.K., Canada, Australia and France or the persons under their jurisdictions according to the agreements concluded between the governments of Japan and these countries, respectively, the nuclear fuel materials recovered from these materials or produced by their usage, nuclear reactors, the facilities and heavy water transferred by sale or other means from these governments or the persons under their jurisdictions, the nuclear fuel materials produced by the usage of such reactors, facilities and heavy water, the nuclear fuel materials sold by the International Atomic Energy Agency under the contract between the Japanese government and the IAEA, the nuclear fuel materials recovered from these materials or produced by their usage, the heavy water produced by the facilities themselves transferred from the Canadian government, Canadian governmental enterprises or the persons under the jurisdiction of the Canadian government or produced by the usage of these facilities, etc. (Okada, K.)

  15. Method to determine the radioactivity of radioactive waste packages. Basic procedure of the method used to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants: 2007

    International Nuclear Information System (INIS)

    2008-03-01

    This document describes the procedures adopted in order to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants in Japan. The standards applied have been approved by the Atomic Energy Society of Japan after deliberations by the Subcommittee on the Radioactivity Verification Method for Waste Packages, the Nuclear Cycle Technical Committee, and the Standards Committee. The method for determining the radioactivity of the low-level radioactive waste packages was based on procedures approved by the Nuclear Safety Commission in 1992. The scaling factor method and other methods of determining radioactivity were then developed on the basis of various investigations conducted, drawing on extensive accumulated knowledge. Moreover, the international standards applied as common guidelines for the scaling factor method were developed by Technical Committee ISO/TC 85, Nuclear Energy, Subcommittee SC 5, Nuclear Fuel Technology. Since the application of accumulated knowledge to future radioactive waste disposal is considered to be rational and justified, such body of knowledge has been documented in a standardized form. The background to this standardization effort, the reasoning behind the determination method as applied to the measurement of radioactivity, as well as other related information, are given in the Annexes hereto. This document includes the following Annexes. Annex 1: (reference) Recorded items related to the determination of the scaling factor. Annex 2 (reference): Principles applied to the determining the radioactivity of waste packages. (author)

  16. Revised thermodynamic properties of brucite determined by solubility studies and its significance to nuclear waste isolation

    International Nuclear Information System (INIS)

    Xiong, Yongliang

    2007-01-01

    MgO is the only engineered barrier certified by EPA for the Waste Isolation Pilot Plant (WIPP) in USA. The German Asse repository will also employ an Mg(OH) 2 (brucite)-based engineered barrier. The chemical function of the engineered barrier is to consume CO 2 that may be generated by the microbial degradation of organic materials in waste packages. Experimental results at SNL indicate that MgO is first hydrated as brucite, and then brucite is carbonated as hydromagnesite (5424) (Mg 5 (CO 3 ) 4 (OH) 2 · 4H 2 O). As MgO is in excess relative to CO 2 that may be produced, the brucite-hydromagnesite (5424) assemblage would buffer f CO2 in the repository. Consequently, the thermodynamic properties of this assemblage is of great significance to the performance assessment (PA) as actinide solubility is strongly affected by f CO2 . In turn, PA is important to the demonstration of the long-term safety of nuclear waste repositories, as assessed by the use of probabilistic performance calculations. There is a substantial discrepancy for Δ f G brucite 0 in recent publications, ranging from -830.4 (Harvie et al., 1984; Geochim. Cosmochim. Acta, 723-751), through -831.9 (Brown et al., 1996; J. Chem. Soc., Dalton Trans., 3071-3075), through -833.5 (Robie and Hemingway, 1995; USGS Bull., 2131), and to -835.9 kJ mol -1 (Konigsberger et al., 1999; Geochim. Cosmochim. Acta, 3105-3119). Using the Δ f G hydromagnesite (5424) 0 from Konigsberger et al., the predicted log f CO2 for this assemblage would range from -5.96 (Δ f G brucite 0 from Harvie et al.) to -4.84 (Δ f G brucite 0 from Konigsberger et al.). Therefore, it is desirable to better constrain the Δ f G brucite 0 . For this reason, a series of solubility experiments involving brucite in NaCl solutions ranging from 0.01 M to 4.0 M have being conducted at SNL. The derived Δ f G brucite 0 from this study by extrapolation to infinite dilution via Pitzer formalism is -830.8 kJ mol -1 , which is in excellent agreement with

  17. Determination of U235 enrichment from nuclear fuel by neutronic activation

    International Nuclear Information System (INIS)

    Almeida, M.C.M. de.

    1988-01-01

    The enrichment of 235 U in UO 2 pellets samples through the instrumental neutron activation analysis method (I.N.A.A.) was determined. By high resolution gamma-ray spectrometry (H.R.G.S.), from analysis of isotopic ratios between fission products peaks from 235 U and 239 Np different energies peaks from 238 U, the enrichment was achieved. The 'Boatstrap' statistics technique for the analytical results, which is based in shaping results of an unknown distribution to the Gaussian distribution by B replications in interested statistics such as: the mean and its standard error, was introduced. (M.J.C.) [pt

  18. Determination of re-aeration coefficients on high mountain rivers using nuclear techniques

    International Nuclear Information System (INIS)

    Fajardo, Marco

    2001-01-01

    The rivers Machangara and Guayllabamba in Quito, Ecuador, currently are highly polluted, mainly due to human and industrial residues from the city. The objective of this survey is to establish the dynamics of dissolved oxygen in these rivers using the Krypton 85 method to determine the re aeration coefficient in representative sectors of the rivers. In addition, conventional test tracers establish mean flow speed and flow longitudinal dispersion coefficients. The results of this study will be useful for future water quality modelling of these rivers, in order to define their behaviour and auto depurative capacity to treat sludge waters from Quito

  19. Preliminary field dose rate determination in the environment of the Paks nuclear power plant

    International Nuclear Information System (INIS)

    Nemeth, I.; Zombori, P.; Koblinger, L.; Andrasi, A.; Deme, S.

    1983-01-01

    The in situ measurements were performed by a NaI(Tl) scintillation spectrometer and a GM detector at 23 points in the environment of the power plant. During the sophisticated calibration procedure the energy and direction dependences of the detector responses were also taken into account. The dose rates were also determined by the POKER-CAMP computer code for natural radionuclides with an assumed source distribution. On the basis of the good agreement between the measured and calculated values the sensitivity of the measuring system was assessed for some given distributed radionuclides released from the power plant. (author)

  20. Determination of performance criteria for high-level solidified nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Heckman, R.A.; Holdsworth, T.

    1979-05-07

    To minimize radiological risk from the operation of a waste management system, performance limits on volatilization, particulate dispersion, and dissolution characteristics of solidified high level waste must be specified. The results show clearly that the pre-emplacement environs are more limiting in establishing the waste form performance criteria than the post-emplacement environs. Absolute values of expected risk are very sensitive to modeling assumptions. The transportation and interim storage operations appear to be most limiting in determining the performance characteristics required. The expected values of risk do not rely upon the repositories remaining intact over the potentially hazardous lifetime of the waste.

  1. Procedure of determination of the nuclear reactor start-up power

    International Nuclear Information System (INIS)

    Brandt, K.D.; Griese, K.; Guehne, F.

    1985-01-01

    The invention has been aimed at a determination of the thermal reactor power during the start-up period and the commissioning resp. preferably under an extremely low thermal power in a range from 0.001 to 1%. In addition to it also the power range up to 100% shall be covered. The external gamma-ray flux density as a function of the thermal reactor power is measured in several overlapping partial measuring ranges. A suitable measuring device transforms the input signals into an electrically measured quantity proportional to the reactor power

  2. Uncertainty of determination of 158Tb in the RBMK nuclear reactor waste.

    Science.gov (United States)

    Plukis, Artūras; Barkauskas, Vytenis; Druteikienė, Rūta; Duškesas, Grigorijus; Germanas, Darius; Gudelis, Arūnas; Juodis, Laurynas; Lagzdina, Elena; Plukienė, Rita; Remeikis, Vidmantas

    2018-04-01

    The activity of 158 Tb was measured in waste samples from the Ignalina NPP Unit I RBMK-1500 reactor using gamma-ray spectrometry. The origin of 158 Tb and the other observed gamma-ray emitters has been studied by using SCALE 6.1 modeling and comparing radionuclide ratios in the RBMK-1500 radioactive waste. The results of the calculation of the massic activity of gamma-ray emitters were used for interpretation of the total gamma-ray spectrum and the determination of 158 Tb massic activity uncertainty in the waste of RBMK-1500. Copyright © 2017 Elsevier Ltd. All rights reserved.

  3. Determination of performance criteria for high-level solidified nuclear waste

    International Nuclear Information System (INIS)

    Heckman, R.A.; Holdsworth, T.

    1979-01-01

    To minimize radiological risk from the operation of a waste management system, performance limits on volatilization, particulate dispersion, and dissolution characteristics of solidified high level waste must be specified. The results show clearly that the pre-emplacement environs are more limiting in establishing the waste form performance criteria than the post-emplacement environs. Absolute values of expected risk are very sensitive to modeling assumptions. The transportation and interim storage operations appear to be most limiting in determining the performance characteristics required. The expected values of risk do not rely upon the repositories remaining intact over the potentially hazardous lifetime of the waste

  4. Determination of xenon in irradiated nuclear fuel using a shielded electron microprobe

    International Nuclear Information System (INIS)

    Jenson, E.D.

    1983-06-01

    The technique described produces a semi-quantitative determination of the distribution of xenon present in a section of fuel pin along a predetermined line. The x-ray counting technique chosen is to drive the spectrometer over the peak in small increments, counting at each step, then to integrate the resulting data over the entire peak. Counting times are usually 10 sec at each step and there are 30 to 40 steps over a peak. Interferences and possible loss of Xe due to local heating are discussed. Comparison with independent analysis is presented

  5. Determination of wall wear of glassmelting furnaces by a nuclear technique

    International Nuclear Information System (INIS)

    Harsanyi, Gyoergy; Kodolanyi, Andras; Leitner, Laszlo

    1984-01-01

    A new in-service inspection technique of glassmelting furnaces is reported. Isotope-labelled refractory tank blocks were prepared, tested experimentally, and built into the furnace. Sup(60)Co isotope tracer was used. The residual wall thickness of the labelled blocks were determined by periodical radiation dose measurements. No environmental or health damage is caused by the specific activity of 3.7 - 4 Bq/g of the labelled furnace blocks, the dose rate in a distance of 1 m from the wall was as low as 0.05 mR/h. (P.J.)

  6. Function- and localisation diagnosis on hyperparathyroidism by radioimmunological parathormone determination and by nuclear scintigraphy

    International Nuclear Information System (INIS)

    Hrubesch, M.; Wagner, H.; Vosberg, H.; Loew, H.; Hauss, W.H.

    1974-01-01

    A function and localization diagnosis of hyperparathyroidism can be made using the RIA and core memory scintigraphy. The combination of these two methods is an important improvement of the diagnostic possibilities in hyperthyroidism. The functional state at the time of investigation can be checked by serum PTH determination. Scintigraphy is important in localization diagnostics in first and third stage hyperparathyroidism but is limited to the cervical region. Second stage hyperparathyroidism as a regulative disturbance - indicated by the drop of the PTH level during haemodialysis - requires conservative therapy. (GSE/AK) [de

  7. Determination of elemental composition of some aphrodisiac herbs by Nuclear Analytical Technique (INAA)

    International Nuclear Information System (INIS)

    Mohammed, L.; Okunade, I.O.; Balogun, G.I.

    2011-01-01

    Fresh medicinal plants that are popularly believed to have aphrodisiac properties were collected in the form of leaves, stem bark, nuts, fruits, seeds, and roots, between 25th September 2009 and 15 October 2009. Instrumental Neutron Activation Analysis (INAA) has been applied to multielemental determination of thirteen aphrodisiac herbs used to treat the problem of Sexual dysfunction. Concentrations of twenty two elements AI, As, Ba, Br, Ca, Co, Cr, Cs, Dy, Eu, Fe, Hf, K, La, Lu, Mg, Mn, Na, Rb, Sb, Sc, Sm, Ta, Th, Ti, U, V, Yb, and Zn have been determined by short and long irradiation times with a thermal neutron flux of 5* 1011ncm-2s-1. Quality control and quality assurance of the method was tested by analyzing IAEA-359 and SRM-1573 together with the samples. The INAA spectra were analyzed using WINSPAN 2004 software package. Our result shows that Euphobia hirta recorded high Zn (669±34 g g-1) which is more than the amount (95.0 g g-1) in Jaipal sex tonic. The level of Fe in Cassytha filiformis, and Indigofera hirsute, is 599 g g-1 and 702 g g-1 respectively. These values are in good agreement with the Fe concentration in the popular aphrodisiac Panax gingseng and Radix codonopsis. For all the species of the same family the correlation coefficients are highly distinctive for each species. The present study can be use to some extent to assess the safety intake of aphrodisiac herbs in the final formulation.

  8. Vanadium in organic fossils as determined by nuclear-physical methods of analysis

    International Nuclear Information System (INIS)

    Nadirov, N.N.; Solodukhin, V.P.

    1998-01-01

    Results are presented of several year investigation to study possibilities of the NPMA for the determination of vanadium in organic fossils and applications of these methods to scientific and practical tasks. For these purposes, various versions of activation analysis (AA), X-ray fluorescence analysis (XRFA), electron spin resonance (ESR) spectroscopy and atomic emission with inductively coupled plasma spectroscopy (AES-ICP). Advantages and pitfalls of individual methods are discussed. The techniques developed can be used for estimation and calculation of stocks of vanadium in organic fossils at the territories of Kazakstan, Tatarstan and along the Volga-river. Analysis results helped in discovering new, industrially important deposits of this valuable metal. Quantitative determination of vanadium was carried out at different stages of technological processes of its extraction from high-viscous oils and oil-bitumen rocks. Results of analyses allowed to reveal the most effective versions of technologies of demetallization of these fossils. Content of vanadium was also studied in different locations of high-viscous oil deposits being explored by the method of inside-stratum burning. Results of analyses showed that the concentration of vanadium in oil decreases considerably with increasing temperature, that is, a considerable part of vanadium (up to 60 percent) may be lost irretrievably. Thus, for the exploration of these deposits a method of vapor-thermal influence onto the stratum was recommended, by using of which the loss of vanadium is insignificant

  9. Determination of contaminants in nuclear materials by measuring the capture gamma rays of thermal neutrons in a reactor internal geometry

    International Nuclear Information System (INIS)

    Suarez, A.A.

    1980-01-01

    A new method for analysis of impurities in nuclear fuel material was developed. Prompt gamma rays following thermal neutron capture, from a sample placed inside the research reactor were analyzed with a solid state high resolution detector. A number of improvements were introduced to improve the background-to-signal ratio, and the sensitivity of the method: use of collimeters for gamma rays and 6 Li 2 CO 3 filters to eliminate thermal neutrons from the beam were supplemented with the application of a pair spectrometer. Using a 42.5 cm 3 true coaxial Ge(Li) detector, and two optically separated NaI (Tl) scintillation detector, the sensitivity of the method for quantitative determination of impurities reached 30 p.p.m. The reproducibility of the results was better than 2%

  10. Determination of lifetimes of nuclear excited states using the Recoil Distance Doppler Shift Method in combination with magnetic spectrometers

    Energy Technology Data Exchange (ETDEWEB)

    Doncel, M. [Universidad de Salamanca, Laboratorio de Radiaciones Ionizantes, Salamanca (Spain); Royal Institute of Technology, Department of Physics, Stockholm (Sweden); University of Liverpool, Department of Physics, Oliver Lodge Laboratory, Liverpool (United Kingdom); Gadea, A. [CSIC-University of Valencia, Istituto de Fisica Corpuscular, Valencia (Spain); Valiente-Dobon, J.J. [INFN, Laboratori Nazionali di Legnaro, Legnaro (Italy); Quintana, B. [Universidad de Salamanca, Laboratorio de Radiaciones Ionizantes, Salamanca (Spain); Modamio, V. [INFN, Laboratori Nazionali di Legnaro, Legnaro (Italy); University of Oslo, Oslo (Norway); Mengoni, D. [Dipartimento di Fisica e Astronomia, Universita di Padova, Padova (Italy); Istituto Nazionale di Fisica Nucleare, Sezione di Padova, Padova (Italy); Moeller, O.; Pietralla, N. [Technische Universitaet Darmstadt, Institut fuer Kernphysik, Darmstadt (Germany); Dewald, A. [Institut fuer Kernphysik, Universitaet Koeln (Germany)

    2017-10-15

    The current work presents the determination of lifetimes of nuclear excited states using the Recoil Distance Doppler Shift Method, in combination with spectrometers for ion identification, normalizing the intensity of the peaks by the ions detected in the spectrometer as a valid technique that produces results comparable to the ones obtained by the conventional shifted-to-unshifted peak ratio method. The technique has been validated using data measured with the γ-ray array AGATA, the PRISMA spectrometer and the Cologne plunger setup. In this paper a test performed with the AGATA-PRISMA setup at LNL and the advantages of this new approach with respect to the conventional Recoil Distance Doppler Shift Method are discussed. (orig.)

  11. Site investigation methods used in Canada's nuclear fuel waste management program to determine the hydrogeological conditions of plutonic rock

    International Nuclear Information System (INIS)

    Davison, C.C.

    1985-01-01

    Atomic Energy of Canada Limited (AECL) is investigating the concept of disposing of Canada's nuclear fuel wastes in a mined vault at a depth of 500 m to 1000 m within a plutonic rock body. Much effort has been directed at developing site investigation methods that can be used to determine the hydrogeological conditions of plutonic rock bodies. The primary objective of this research is to define the physical and chemical characteristics of groundwater flow systems at the various scales that are relevant to the prediction of potential radionuclide migration from a disposal vault. Groundwater movement through plutonic rock is largely controlled by fractures within the rock, and the hydrogeological parameters of fractured geological media are extremely scale dependent

  12. Determination of the excess of reactivity in a nuclear configuration and its influence on the power level

    International Nuclear Information System (INIS)

    Zuniga, Agustin; Tapia, Jose

    2014-01-01

    This work presents experimental results which show that the critical position of a given nuclear configuration changes with the reactor power (expressed by the current measurement). Thus, if the current is 0.6 x 10 -11 A (1 W), then the critical position is, BC1 = 0.0 % while 0.6 x 10 -9 A (100 W), BC1= 46.5 %. The difference is apparent because under a current of 10 -10 A, the reactivity is not significant. Therefore, it is recommended that for reactors like the RP-10 with a lot of neutrons at the 'background' level, the excess reactivity must be measured in current as 0.6 x 10 -9 A (100 W) not less. Finally, the excess of reactivity for the N o 42 configuration was determined, which was 3032 pcm with uncertainty less than 1 %. (authors).

  13. On the principles of the determination of the safe shut-down earthquake for nuclear power plants in Austria

    International Nuclear Information System (INIS)

    Drimmel, J.

    1976-01-01

    At present no legal guide lines exist in Austria for the determination of the Safe Shut-Down Earthquake. According to experience, the present requirements for a nuclear power plant site are the following: It must be free of marked tectonic faults and it must never have been situated within the epicentral region of a strong earthquake. The maximum expected earthquake and the Safe Shut-Down Earthquake respectively, are fixed by the aid of a frequency map of strong earthquakes and a map of extreme earthquake intensities in Austria based on macroseismic data since 1201 A.D. The corresponding values of acceleration will be prescribed according to the state of science, but must at least be 0.10 g for the horizontal and 0.05 g for the vertical component of acceleration at the basement

  14. A study on determination methods of fueling machine heavy water supply setpressure for Wolsong nuclear power plant unit 1

    International Nuclear Information System (INIS)

    Kim, J. M.; Jeong, B. Y.; Baek, S. J.; Noh, T. S.; Kim, Y. H.; Park, W. K.

    2001-01-01

    The present Wolsong 1 Fuel Handling (F/H)D 2 O Supply Pressure Control System, based on an analog cascaded Proportional-Integral-Differential (PID) control, is less accurate and requires more labor for test and maintenance in comparison with up-to-data digital controllers. Furthermore, F/H operator and technical staff have recently encountered difficulties in operation and maintenance because of frequent occurrences of system instability and failure, and obsolescence of hardware. However the analysis and design review of F/H D 2 O Supply Pressure Control System have not been performed appropriately. Therefore, the design review of F/H D 2 O Supply Pressure Control System has been thoroughly reviewed and analyzed. Based on the analysis results, the optimum pressure setpoints and its determination methods have been proposed for Wolsong Nuclear Power Plant Unit 1

  15. Validated ¹H and 13C Nuclear Magnetic Resonance Methods for the Quantitative Determination of Glycerol in Drug Injections.

    Science.gov (United States)

    Lu, Jiaxi; Wang, Pengli; Wang, Qiuying; Wang, Yanan; Jiang, Miaomiao

    2018-05-15

    In the current study, we employed high-resolution proton and carbon nuclear magnetic resonance spectroscopy (¹H and 13 C NMR) for quantitative analysis of glycerol in drug injections without any complex pre-treatment or derivatization on samples. The established methods were validated with good specificity, linearity, accuracy, precision, stability, and repeatability. Our results revealed that the contents of glycerol were convenient to calculate directly via the integration ratios of peak areas with an internal standard in ¹H NMR spectra, while the integration of peak heights were proper for 13 C NMR in combination with an external calibration of glycerol. The developed methods were both successfully applied in drug injections. Quantitative NMR methods showed an extensive prospect for glycerol determination in various liquid samples.

  16. A study on the determination of threshold values for the initiating event performance indicators of domestic nuclear power plants

    International Nuclear Information System (INIS)

    Kang, D. I.; Park, J. H.; Kim, K. Y.; Whang, M. J.; Yang, J. E.; Sung, G. Y.

    2003-01-01

    In this paper, we determine the threshold values of unplanned reactor scram, domestic initiating event performance indicator, using data of domestic unplanned reactor scram and probabilistic safety assessment model of Korea Standard Nuclear Power Plant(KSNP). We also perform a pilot study of initiating event Risk Based Performance Indicator(RBPI) for KSNP. Study results for unplanned reactor scram show that the threshold value of between green and blue color is 3, that of between blue and yellow color is 6, and that of between yellow and orange color is 30. Pilot study results of initiating event RBPI show that loss of feedwater, transient, and loss of component cooling water events are selected as initiating event RBPI for KSNP

  17. Validation Study for an Atmospheric Dispersion Model, Using Effective Source Heights Determined from Wind Tunnel Experiments in Nuclear Safety Analysis

    Directory of Open Access Journals (Sweden)

    Masamichi Oura

    2018-03-01

    Full Text Available For more than fifty years, atmospheric dispersion predictions based on the joint use of a Gaussian plume model and wind tunnel experiments have been applied in both Japan and the U.K. for the evaluation of public radiation exposure in nuclear safety analysis. The effective source height used in the Gaussian model is determined from ground-level concentration data obtained by a wind tunnel experiment using a scaled terrain and site model. In the present paper, the concentrations calculated by this method are compared with data observed over complex terrain in the field, under a number of meteorological conditions. Good agreement was confirmed in near-neutral and unstable stabilities. However, it was found to be necessary to reduce the effective source height by 50% in order to achieve a conservative estimation of the field observations in a stable atmosphere.

  18. Using the nuclear activation AMS method for determining chlorine in solids at ppb-levels and below

    International Nuclear Information System (INIS)

    Winkler, Stephan R.; Eigl, Rosmarie; Forstner, Oliver; Martschini, Martin; Steier, Peter; Sterba, Johannes H.; Golser, Robin

    2015-01-01

    Neutron activation analysis using decay counting of the activated element is a well-established method in elemental analysis. However, for chlorine there is a better alternative to measuring decay of the short-lived activation product chlorine-38 (t 1/2 = 37.24 min) – accelerator mass spectrometry (AMS) of 36 Cl: the relatively high neutron capture cross section of chlorine-35 for thermal neutrons (43.7 b) and combined the AMS technique for chlorine-36 (t 1/2 = 301 ka) allow for determination of chlorine down to ppb-levels using practical sample sizes and common exposure durations. The combination of neutron activation and AMS can be employed for a few other elements (nitrogen, thorium, and uranium) as well. For bulk solid samples an advantage of the method is that lab contamination can be rendered irrelevant. The chlorine-35 in the sample is activated to chlorine-36, and surface chlorine can be removed after the irradiation. Subsequent laboratory contamination, however, will not carry a prominent chlorine-36 signature. After sample dissolution and addition of sufficient amounts of stable chlorine carrier the produced chlorine-36 and thus the original chlorine-35 of the sample can be determined using AMS. We have developed and applied the method for analysis of chlorine in steel samples. The chlorine content of steel is of interest to nuclear industry, precisely because of above mentioned high neutron capture cross section for chlorine-35, which leads to accumulation of chlorine-36 as long-term nuclear waste. The samples were irradiated at the TRIGA Mark II reactor of the Atominstitut in Vienna and the 36 Cl-AMS setup at the Vienna Environmental Research Accelerator (VERA) was used for 36 Cl/Cl analysis.

  19. Using the nuclear activation AMS method for determining chlorine in solids at ppb-levels and below

    Energy Technology Data Exchange (ETDEWEB)

    Winkler, Stephan R., E-mail: srw@tlabs.ac.za [Universität Wien, Fakultät für Physik, Institut für Isotopenforschung und Kernphysik (Austria); Eigl, Rosmarie [Universität Wien, Fakultät für Chemie, Institut für Anorganische Chemie (Austria); Forstner, Oliver; Martschini, Martin; Steier, Peter [Universität Wien, Fakultät für Physik, Institut für Isotopenforschung und Kernphysik (Austria); Sterba, Johannes H. [Technische Universität Wien, Atominstitut (Austria); Golser, Robin [Universität Wien, Fakultät für Physik, Institut für Isotopenforschung und Kernphysik (Austria)

    2015-10-15

    Neutron activation analysis using decay counting of the activated element is a well-established method in elemental analysis. However, for chlorine there is a better alternative to measuring decay of the short-lived activation product chlorine-38 (t{sub 1/2} = 37.24 min) – accelerator mass spectrometry (AMS) of {sup 36}Cl: the relatively high neutron capture cross section of chlorine-35 for thermal neutrons (43.7 b) and combined the AMS technique for chlorine-36 (t{sub 1/2} = 301 ka) allow for determination of chlorine down to ppb-levels using practical sample sizes and common exposure durations. The combination of neutron activation and AMS can be employed for a few other elements (nitrogen, thorium, and uranium) as well. For bulk solid samples an advantage of the method is that lab contamination can be rendered irrelevant. The chlorine-35 in the sample is activated to chlorine-36, and surface chlorine can be removed after the irradiation. Subsequent laboratory contamination, however, will not carry a prominent chlorine-36 signature. After sample dissolution and addition of sufficient amounts of stable chlorine carrier the produced chlorine-36 and thus the original chlorine-35 of the sample can be determined using AMS. We have developed and applied the method for analysis of chlorine in steel samples. The chlorine content of steel is of interest to nuclear industry, precisely because of above mentioned high neutron capture cross section for chlorine-35, which leads to accumulation of chlorine-36 as long-term nuclear waste. The samples were irradiated at the TRIGA Mark II reactor of the Atominstitut in Vienna and the {sup 36}Cl-AMS setup at the Vienna Environmental Research Accelerator (VERA) was used for {sup 36}Cl/Cl analysis.

  20. Determination of 99Mo in 99mTc eluates used in nuclear medicine centers in Rio de Janeiro

    International Nuclear Information System (INIS)

    Ribeiro, Bianca da S.; Souza, Raphael S.S.; Lucena, Eder A.; Dantas, Ana Leticia A.; Dantas, Bernardo M.

    2009-01-01

    99m Tc is used in nuclear medicine for image diagnoses with SPECT. It is obtained from the elution of molybdenum-99/technetium-99m ( 99 Mo/ 99m Tc) generators. During the elution, 99 Mo can detach from the column, passing through the filter and mixing in the solution of pertechnetate eluate and becoming a radionuclidic impurity. The presence of molybdenum in the radiopharmaceutical solution imparts an unnecessary radiation dose to the patient, since its half-life is relatively long (66 hours) and it emits beta particles and high-energy photons of (740 keV). A parameter that indicates the quality of the eluates is the radionuclidic purity, the MBT (molybdenum break through), defined as the ratio between 99 Mo and 99m Tc activities in the eluate. The American and the European Pharmacopoeias restrict 99 Mo content to respectively 0.015% and 0.1% activity ratio 99 Mo/ 99m Tc at the time of the administration to the patient. In Brazil, this parameter is not controlled by official regulations. The objective of this work is to determine the presence of 99 Mo in the eluates used in nuclear medicine centers (NMC). The activity measurements of 99 Mo were performed with a NaI(Tl)8''x4'' scintillation detector installed in the IRD whole body counter. The activity of 99m Tc was measured in the NMC where the eluates were collected and, using the established calculations, it was determined the activity ratio 99 Mo/ 99m Tc. The eluate samples were kindly supplied by the participating NMC of Rio de Janeiro. All measurements indicated the presence of 99 Mo. It is concluded that the technique is sensitive to detect 99 Mo in 99m Tc eluates and permits to verify the quality of the generators used in NMC evaluated in this study. (author)

  1. Using the nuclear activation AMS method for determining chlorine in solids at ppb-levels and below

    Science.gov (United States)

    Winkler, Stephan R.; Eigl, Rosmarie; Forstner, Oliver; Martschini, Martin; Steier, Peter; Sterba, Johannes H.; Golser, Robin

    2015-10-01

    Neutron activation analysis using decay counting of the activated element is a well-established method in elemental analysis. However, for chlorine there is a better alternative to measuring decay of the short-lived activation product chlorine-38 (t1/2 = 37.24 min) - accelerator mass spectrometry (AMS) of 36Cl: the relatively high neutron capture cross section of chlorine-35 for thermal neutrons (43.7 b) and combined the AMS technique for chlorine-36 (t1/2 = 301 ka) allow for determination of chlorine down to ppb-levels using practical sample sizes and common exposure durations. The combination of neutron activation and AMS can be employed for a few other elements (nitrogen, thorium, and uranium) as well. For bulk solid samples an advantage of the method is that lab contamination can be rendered irrelevant. The chlorine-35 in the sample is activated to chlorine-36, and surface chlorine can be removed after the irradiation. Subsequent laboratory contamination, however, will not carry a prominent chlorine-36 signature. After sample dissolution and addition of sufficient amounts of stable chlorine carrier the produced chlorine-36 and thus the original chlorine-35 of the sample can be determined using AMS. We have developed and applied the method for analysis of chlorine in steel samples. The chlorine content of steel is of interest to nuclear industry, precisely because of above mentioned high neutron capture cross section for chlorine-35, which leads to accumulation of chlorine-36 as long-term nuclear waste. The samples were irradiated at the TRIGA Mark II reactor of the Atominstitut in Vienna and the 36Cl-AMS setup at the Vienna Environmental Research Accelerator (VERA) was used for 36Cl/Cl analysis.

  2. Determination of radiostrontium released from Fukushima Daiichi Nuclear Power Plant through extraction chromatography and liquid scintillation counting

    International Nuclear Information System (INIS)

    Maekawa, Akihiro; Momoshima, Noriyuki; Sugihara, Shinji; Tamari, Toshiya

    2013-01-01

    Two soil samples were collected on April 18-20, 2011 at Namie town and Tomioka town, which are located 26 km northwest and 11 km south of the Fukushima Daiichi Nuclear Power Plant, respectively. A 0-1 cm soil layer was used for analysis to determine the presence of radiostrontium. The soil was ashed, acid-digested, and strontium was separated from interference with use of an extraction chromatography resin (Sr resin, Eichrom Technologies). The isolation and purification of strontium from matrix components can be completed in 12 h. After 2 weeks for ingrowth of "9"0Y, measurements of a beta-ray of "9"0Y and "8"9"+"9"0Sr were conducted with a low-background liquid-scintillation counter for 1200 min. The concentration of "9"0Sr was determined to be 57.4 ± 1.0 and 10.1 ± 0.4 Bq kg"-"1 for Namie town and Tomioka town, respectively. "8"9Sr was not detected in either sample. The extraction chromatography method was successfully applied to determine the level of radiostrontium in the contaminated soil. When 2 g of soil is used, the detection limit of "9"0Sr is evaluated to be 2.7 Bq kg"-"1 under a chemical yield of strontium of 70%. (author)

  3. U.S. Nuclear Regulatory Commission Role and Activities Related to U.S. Department of Energy Incidental Waste Determinations

    International Nuclear Information System (INIS)

    Bradford, A.H.; Esh, D.W.; Ridge, A.C.

    2006-01-01

    Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) requires the U.S. Department of Energy (DOE) to consult with the U.S. Nuclear Regulatory Commission (NRC) for certain non-high level waste (HLW) determinations. Under the NDAA, NRC performs consultative technical reviews of DOE's waste determinations and monitors DOE's disposal actions for such waste, but the NRC does not have regulatory authority over DOE's waste disposal activities. The NDAA provides the criteria that must be met to determine that waste is not HLW. The criteria require that the waste does not need to be disposed of in a geologic repository, that highly radioactive radionuclides be removed to the maximum extent practical, and that the performance objectives of 10 CFR 61, Subpart C, be met. The performance objectives contain criteria for protection of the public, protection of inadvertent intruders, protection of workers, and stability of the disposal site after closure. This paper describes NRC's approach to implementing its responsibilities under the NDAA, as well as similar activities being performed for sites not covered by the NDAA. (authors)

  4. The use of nuclear related analytical techniques for the determination of ingestion and body content of trace elements

    International Nuclear Information System (INIS)

    Djojosubroto, H.; Santoso, D.; Widjajakusuma, B.

    1998-01-01

    A number of observations revealed that various human disease states are associated with measurable abnormalities of trace element levels. Until present there is no data on trace element levels in human tissues and dietary intake representing the population in Indonesia. Trace element level in various biological materials, especially human serum related to health syndrome (e.g. acute myocardial infarction and goiter prevalences) was performed by National Atomic Energy Agency in cooperation with relevant institutes. The present study is concerned with determination of ingestion and organ content of trace elements of importance in radiological protection (Cs, Sr, I, Th and U). Quantitation of the elements in the samples will be determined by neutron activation analysis, complemented by nuclear related analytical techniques, e.g. inductively coupled plasma - mass spectrometry and atomic absorption spectrometry. Samples to be analyzed consist of (a) total diets and individual staple foodstuffs, (b) autopsy specimens of liver, lung, kidney, muscle, thyroid and bone, and (c) drinking water. It seems difficult for us to define nationally representative specimens of total diets and individual staple foodstuffs. Based on these facts, in the first year activity samples of dietary intake from various socio economic levels of population in West Java will be collected. Human tissue sample is obtained from autopsy of normal persons who are killed in traffic accident or homicide victim. Traces of Th and U in drinking water are determined by neutron activation analysis following preconcentration of these elements in chelating resin Chlelex 100. (author)

  5. Determination of hydrogen concentration in amorphous silicon films by nuclear elastic scattering (NES) of 100 MeV 3He2+

    International Nuclear Information System (INIS)

    Iwami, M.; Imura, T.; Hiraki, A.

    1981-01-01

    Nuclear elastic scattering (NES) of 100 MeV 3 He 2+ ions was used to determine the amount of hydrogen atoms in hydrogenated amorphous silicon film fabricated by reactive sputtering. The total amount of hydrogen in this film was determined to be (1.12 +- 0.1) x 10 22 cm -3 within the accuracy of approximately 10%. (author)

  6. Single-column ion chromatography with determination of hydrazoic acid produced in spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Ma Guilan; Tan Shuping

    2006-01-01

    The reaction of hydrazine and its derivative with ammonium metavanadate may produce hydrazoic acid (HN 3 ). A single-column ion chromatography is used for the determination of HN 3 after neutralizing the rest acid in the sample with sodium hydroxide. Chromatography separation of HN 3 is carried out on a 25 cm x 0.46 cm (inside diameter) stainless steel column packed with Vydac IC302 ion Chromatography packing. The eluent is 1 mmol/L o-phthalic acid, and the ion is detected by conductivity detector. The detection limit in the presence chromatography is 5 μg/mL, the linear range is from 5 to 201 μg/mL, the linear correlation coefficient is 0.9994, respectively. The analysis accuracy is 2% for standard sample, and the detection limit is 51 μg/mL for HN 3 in the real sample. (authors)

  7. Spectrographic determination of impurities in ceramic materials for nuclear fusion reactors. 1. Analysis of alumina

    International Nuclear Information System (INIS)

    Rucandio, M.I.; Roca, M.; Melon, A.

    1990-01-01

    The determination of minor and trace elements in the aluminium oxide considered as possible ceramic material in thermonuclear fusion reactors has been studied. The concentration ranges are 0.1-0.3 % for Ca, Si and Y, and at the ppm level for Co, Cr, Fe, Hf, K, Li, Mg, Mn, Na, Ni, Sc, Ta, Ti, V and Zr. Atomic emission spectroscopy with direct current arc excitation and photographic detection has been employed. For Hf, Mg, Ta, Ti, V and Zr the use of 40% of copper fluoride as a carrier and of Nb as internal standard provide suitable sensitivities and precissions, while for the rest of elements the best results are obtained with graphite powder in different proportions and Rb or Sn as internal standard. (Author). 7 refs

  8. Spectrographic Determination of Impurities in Ceramic Materials for Nuclear fusion Reactors. II. Analysis of Magnesium Aluminate

    International Nuclear Information System (INIS)

    Rucandio, M. I.; Roca, M.; Melon, A.

    1990-01-01

    The determination of minor and trace elements in the magnesium aluminate, considered as possible material in thermonuclear fusion reactors, has been studied. The concentration ranges are 0.1 - 0.3 % for Ca, SI and Y, and at the ppm level for Co, Cr, Fe, Hf, K, Li, Mn, Na, Ni, Se, Ta, Ti, V and Zr. Atomic emission spectroscopy with direct current are excitation and photographic detection has been employed. For Hf, Ta and Zr the use of 40% of copper fluoride as a carrier and of Nb as internal standard provide suitable sensitivities and precessions, while for the rest of elements the best results are obtained with graphite powder in different proportions and Rb or Sn as internal standard. (Author)4 refs

  9. Spectrographic determination of impurities in ceramic materials for nuclear fusion reactors. II. Analysis of magnesium aluminate

    International Nuclear Information System (INIS)

    Roca, M.; Rucandio, M.I.; Melon, A.

    1990-01-01

    The determination of minor and trace elements in the magnesium aluminate, considered as possible mataerial in thermonuclear fusion reactors, has been studied. The concentaration ranges are 0.1-0.3 % for Ca, Si and Y, and at the ppm level for Co, Cr, Fe, Hf, K, Li, Mn, Na, Ni, Sc, Ta, Ti, V and Zr. Atomic emission spectroscopy with direct current arc excitation and photographic detection has been employed. For Hf, Ta and Zr the use of 40% of copper fluoride as a carrier and of Nb as internal standard provide suitable sensitivities and precissions, while for the rest of elements the best results are obtained with graphite power in different proportions and Rb or Sn as internal standard. (Author). 4 refs

  10. Detailed determination of the fusion nuclear radius in reactions involving weakly bound projectiles

    International Nuclear Information System (INIS)

    Gomez Camacho, A.; Aguilera, E. F.; Quiroz, E. M.

    2007-01-01

    A detailed determination of the fusion radius parameter is performed within the Distorted Wave Born Approximation for reactions involving weakly bound projectiles. Specifically, a simultaneous X 2- analysis of elastic and fusion cross section data is done using a Woods-Saxon potential with volume and surface parts. The volume part is assumed to be responsible for fusion reactions while the surface part for all other direct reactions. It is proved that in order to fit fusion data, particularly for energies below the Coulomb barrier where fusion is enhanced, it is necessary to have a value of around 1.4 fm for the fusion radial parameter of the fusion potential (W F ). This value is much higher than that frequently used in Barrier Penetration models (1.0 fm). The calculations are performed for reactions involving the weakly bound projectile 9 Be with several medium mass targets. (Author)

  11. Solution structure of apamin determined by nuclear magnetic resonance and distance geometry

    Energy Technology Data Exchange (ETDEWEB)

    Pease, J.H.B.; Wemmer, D.E.

    1988-11-01

    The solution structure of the bee venom neurotoxin apamin has been determined with a distance geometry program using distance constraints derived from NMR. Twenty embedded structures were generated and refined by using the program DSPACE. After error minimization using both conjugate gradient and dynamics algorithms, six structures had very low residual error. Comparisons of these show that the backbone of the peptide is quite well-defined with the largest rms difference between backbone atoms in these structures of 1.34 /Angstrom/. The side chains have far fewer constraints and show greater variability in their positions. The structure derived here is generally consistent with the qualitative model previously described, with most differences occurring in the loop between the ..beta..-turn (residues 2-5) and the C-terminal ..cap alpha..-helix (residues 9-17). Comparisons are made with previously derived models from NMR data and other methods.

  12. Solution structure of apamin determined by nuclear magnetic resonance and distance geometry

    International Nuclear Information System (INIS)

    Pease, J.H.B.; Wemmer, D.E.

    1988-01-01

    The solution structure of the bee venom neurotoxin apamin has been determined with a distance geometry program using distance constraints derived from NMR. Twenty embedded structures were generated and refined by using the program DSPACE. After error minimization using both conjugate gradient and dynamics algorithms, six structures had very low residual error. Comparisons of these show that the backbone of the peptide is quite well-defined with the largest rms difference between backbone atoms in these structures of 1.34 /Angstrom/. The side chains have far fewer constraints and show greater variability in their positions. The structure derived here is generally consistent with the qualitative model previously described, with most differences occurring in the loop between the β-turn (residues 2-5) and the C-terminal α-helix (residues 9-17). Comparisons are made with previously derived models from NMR data and other methods

  13. Determination of Rare Earth Elements in Thai Monazite by Inductively Coupled Plasma and Nuclear Analytical techniques

    International Nuclear Information System (INIS)

    Busamongkol, Arporn; Ratanapra, Dusadee; Sukharn, Sumalee; Laoharojanaphand, Sirinart

    2003-10-01

    The inductively coupled plasma atomic emission spectroscopy (ICP-AES) for the determination of individual rare-earth elements (REE) was evaluated by comparison with instrumental neutron activation analysis (INAA) and x-ray fluorescence spectrometry (XRF). The accuracy and precision of INAA and ICP-AES were evaluated by using standard reference material IGS-36, a monazite concentrate. For INAA, the results were close to the certified value while ICP-AES were in good agreement except for some low concentration rare earth. The techniques were applied for the analysis of some rare earth elements in two Thai monazite samples preparing as the in-house reference material for the Rare Earth Research and Development Center, Chemistry Division, Office of Atoms for Peace. The analytical results obtained by these techniques were in good agreement with each other

  14. Multielement determination in Cuban red mangrove samples using nuclear and related analytical techniques

    International Nuclear Information System (INIS)

    Estevez Alvarez, J.R.; Aguiar Lambert, D.; Montero Alvarez, A.; Pupo Gonzalez, I.; Padilla Alvarez, R.; Gonzalez Garcia, H.; Ramirez Sasco, M.

    1998-01-01

    In the present work the contents of Al; K; Ca; Mn; Fe; Ni; Cu; Zn; Sr; Cd and Pb in red mangroves (Rhizophora mangle) from different Cuban regions are determined, using Energy Dispersive X-Ray Fluorescence (Emission-Transmission (Et) and I/C methods), Atomic Absorption Spectrophotometry (AAS), and Polarography (Anodic Stripping Voltametry method). Biological Certified Reference Materials (CRM) are employed for the tracing of the tracing of the curves of the relative I/C method and for the evaluation of the analytical results accuracy. The reliability of the results is also checked by statistical means. Standard deviations and the detection limits of each method are reported. Finally, the obtained values for the concentration of the different elements in each studied ecosystem are presented; a detailed discussion about their significance will be performed in a further paper

  15. Spectrographic Determination of Impurities in Ceramic Materials for Nuclear Fusion Reactors. I. Analysis of Alumina

    International Nuclear Information System (INIS)

    Rucandio, M. I.; Roca, M.; Melon, A.

    1990-01-01

    The determination of minor and trace elements in the aluminium oxide considered as possible ceramic material in thermonuclear fusion reactors has been studied. The concentration ranges are 0.1 - 0.3 * for Ca, Si and Y, and at the ppm level for Co, Cr, Fe, Hf, K, Li, Mg, Mn, Na, Ni, Se, Ta, Ti, V and Zr. Atomic emission spectroscopy with direct current ore excitation and photographic detection has been employed. For Hf, Mg, Ta, Ti, V and Zr the use of 40% of copper fluoride as a carrier and of Nb as lnternal standard provide suitable sensitivities and precessions, while for the rest of elements the bent results are obtained with graphite powder in different proportions and Rb or Sn as internal standard. (Author) 7 refs

  16. Determination of tritium concentrations in humans before the development of a nuclear power plant in Turkey.

    Science.gov (United States)

    Dizman, Serdar; Yilmaz, Adnan; Keser, Recep

    2015-01-01

    The most widely used method to determine the level of tritium in humans is testing urine. Tritium concentrations in urine samples of 100 persons aged 18-66 years selected randomly from a pilot region in Turkey were analysed. The average activity concentration of urine samples was 4.66 ± 1.94 Bq L(-1) and the maximum activity concentration was 27.91 Bq L(-1). The minimum detectable activity was 2.38 Bq L(-1). The annual effective dose from tritium was also evaluated on the basis of the measurement results and reference values recommended by the International Commission on Radiological Protection. The effective doses for males and females were 4.56 and 3.54 nSv, respectively. These results were lower than the permissible annual effective dose for members of the public.

  17. Determination of radiation doses caused by release into the atmosphere by nuclear power plants, based on measurement of emission and immission

    International Nuclear Information System (INIS)

    Ekler, B.; Deme, S.

    2006-01-01

    The radiation impact of nuclear facilities, and the nuclear power plants as well, can be determined by using two methods. The first one calculates the dose of critical group of population based on the release, meteorological and hydrological parameters. The second method gives an estimate of the additional dose caused by the nuclear facility from the radiological measurements in the environment. This article compares this two methods for the release in the atmosphere, and gives an estimate of the relative error. The comparison can be applied for cases when the atmospheric pollution is released from a point type source, so for the conventional power plants as well. (author)

  18. In-situ determination of moisture in road pavement by nuclear methods

    International Nuclear Information System (INIS)

    Gray, G.W.; Sowerby, B.D.; Youdale, G.P.

    1981-04-01

    The use of neutron moisture probes to determine moisture in compacted pavement layers has been studied on samples representative of those used by the New South Wales Department of Main Roads for roadway construction. The aim of this work was to measure the average moisture content of the upper layer (15-20 cm thick) with minimum interference from moisture in underlying layers. Sub-surface probes using high (α-Be) and low (α-Li) energy neutron sources were examined; conventional α-Be sources in specially designed compact probes should result in an error due to base moisture and density variations of less than 0.4 wt % moisture. As this error is probably less than those due to sampling and geometry variations in the field, such a probe should be sufficiently accurate for DMR requirements. If less sensitivity to base moisture is required, the α-Li source will reduce this sensitivity by a factor of about 1.4

  19. Determination of selenium mineral in health supplement products: Applications of nuclear methods in pharmaceuticals fields

    International Nuclear Information System (INIS)

    Titiek Martati; Mellawati

    2010-01-01

    Recently, many health supplement products that are useful as an antioxidant available in the market, and one of them is selenium (Se) tablet. Issue on the falsification of drug due to control to health supplement product becomes very important. There is also some problem in Se analysis, especially in chemical reagent preparation. In this research, determination of Se in health supplement tablet using neutron activation analysis (NAA) was carried out. The advantages of methods are due to nondestructive materials, simple sample preparation, and no chemical reagent for analysis. The sample was irradiated using thermal neutron with 10"1"3 neutron cm"-"2 seconds"-"1 fluxes during 15 minutes, and based on n, γ reaction "7"5Se isotope would be formed that could identified using gamma spectrometer on 136, 264, and 279 keV energies. The result showed that NAA method can be used for Se analysis contained in health supplement tablets with accuracy ranged between 101.81 and 102.29 % and precision 99.02-99.37 %. The recovery test of Se mineral concentration to the labeled attached showed 105.79-116.66 %, and this value still in the range described in the United States Pharmacopoeias 28 (90-125 %). (author)

  20. Determination of plutonium and uranium in mixed nuclear fuel by means of potentiostatic and amperostatic coulometry

    International Nuclear Information System (INIS)

    Kuperman, A.Ya.; Moiseev, I.V.; Galkina, V.N.; Yakushina, G.S.; Nikitskaya, V.N.

    1977-01-01

    Product solution occurs in HClO 4 + HNO 3 mixing. In prepared plutonium (6) and uranium (6) perchloric acid solution Cl and Cr (6), Mn (7,6,3) foreign oxidizers are selectively reduced with formic and malonic acids. Potentiostatic variant of method is based on successive reduction of Pu(6) to Pu(3) and U(6) to U(4) in 4.5M HCl, containing 5x10 -4 M bismuth (3). In using amperostatic variant of method plutonium and uranium are determined separately. In sulfur-phosphoric acid media plutonium (6) is titrated to Pu(4) with continuously generated iron (2) ions. Uranium (6) in phosphoric acid media is initially reduced to U(4) with Fe(2), and then after Fe(2) excess reduction with nitric acid it is titrated to uranium (6) with continuously electrogenerated manganese (3) ions or vanadium (5). To obtain equivalent point in plutonium (6) and uranium (4) titration amperometric method is used. Coefficient of variation is 0.2-0.3 % rel

  1. Automated sample-processing and titration system for determining uranium in nuclear materials

    International Nuclear Information System (INIS)

    Harrar, J.E.; Boyle, W.G.; Breshears, J.D.; Pomernacki, C.L.; Brand, H.R.; Kray, A.M.; Sherry, R.J.; Pastrone, J.A.

    1977-01-01

    The system is designed for accurate, precise, and selective determination of from 10 to 180 mg of uranium in 2 to 12 cm 3 of solution. Samples, standards, and their solutions are handled on a weight basis. These weights, together with their appropriate identification numbers, are stored in computer memory and are used automatically in the assay calculations after each titration. The measurement technique (controlled-current coulometry) is based on the Davies-Gray and New Brunswick Laboratory method, in which U(VI) is reduced to U(IV) in strong H 3 PO 4 , followed by titration of the U(IV) with electrogenerated V(V). Solution pretreatment and titration are automatic. The analyzer is able to process 44 samples per loading of the sample changer, at a rate of 4 to 9 samples per hour. The system includes a comprehensive fault-monitoring system that detects analytical errors, guards against abnormal conditions which might cause errors, and prevents unsafe operation. A detailed description of the system, information on the reliability of the component subsystems, and a summary of its evaluation by the New Brunswick Laboratory are presented

  2. Chemical aspects of the precise and accurate determination of uranium and plutonium from nuclear fuel solutions

    International Nuclear Information System (INIS)

    Heinonen, O.J.

    1981-01-01

    A method for the simultaneous or separate determination of uranium and plutonium has been developed. The method is based on the sorption of uranium and plutonium as their chloro complexes on Dowex 1x10 column. When separate uranium and plutonium fractions are desired, plutonium ions are reduced to Pu (III) and eluted, after which the uranium ions are eluted with dilute HCl. Simultaneous stripping of a mass ratio U/Pu approximately 1 fraction for mass spectrometric measurements is achieved by proper choice of eluant HC1 concentration. Special attention was paid to the obtaining of americium free plutonium fractions. The distribution coefficient measurements showed that at 12.5-M HCl at least 30 % of americium ions formed anionic chloro complexes. The chemical aspects of isotopic fractionation in a multiple filament thermal ionization source were also investigated. Samples of uranium were loaded as nitrates, chlorides, and sulphates and the dependence of the measured uranium isotopic ratios on the chemical form of the loading solution as well as on the filament material was studied. Likewise the dependence of the formation of uranium and its oxide ions on various chemical and instrumental conditions was investigated using tungsten and rhenium filaments. Systematic errors arising from the chemical conditions are compared with errors arising from the automatic evaluation of of spectra. (author)

  3. The effect of nuclear gas distribution on the mass determination of supermassive black holes

    Science.gov (United States)

    Mejía-Restrepo, J. E.; Lira, P.; Netzer, H.; Trakhtenbrot, B.; Capellupo, D. M.

    2018-01-01

    Supermassive black holes reside in the nuclei of most galaxies. During their active episodes, black holes are powered by accretion discs where gravitational energy is converted into radiation1. Accurately determining black hole masses is key to understand how the population evolves over time and how the black holes relate to their host galaxies2-4. Beyond the local universe, z ≳ 0.2, the mass is commonly estimated assuming a virialized motion of gas in the close vicinity of the active black holes, traced through broad emission lines5,6. However, this procedure has uncertainties associated with the unknown distribution of the gas clouds. Here, we show that the black hole masses derived from the properties of the accretion disk and virial mass estimates differ by a factor that is inversely proportional to the width of the broad emission lines. This leads to virial mass misestimations up to a factor of six. Our results suggest that a planar gas distribution that is inclined with respect to the line of sight may account for this effect. However, radiation pressure effects on the distribution of gas can also reproduce our results. Regardless of the physical origin, our findings contribute to mitigating the uncertainties in current black hole mass estimations and, in turn, will help us to better understand the evolution of distant supermassive black holes and their host galaxies.

  4. Determination of alpha effectiveness in ESR dating using nuclear accelerator techniques: methods and energy dependence

    International Nuclear Information System (INIS)

    Lyons, R.G.

    1988-01-01

    An important parameter in calculating the environmental dose rate for electron spin resonance (ESR) age estimates is the relative effectiveness of alpha and gamma radiation. A small research accelerator is used as a source of alpha particles of various pre-selected energies, corresponding to those found in the environment, to determine the effectiveness of alpha radiation of different energies. Preparation of sample targets is discussed, including the use of absolute ethanol, thorough etching and deposition by centrifuge. Preliminary results show that the alpha/gamma effectiveness ratio, k, depends on the energy of the incident alpha and must therefore be expressed in terms of a reference energy. The effectiveness of an alpha particle in causing ESR damage is found to vary linearly with its range or path length, not with its energy, a fact which must be considered when calculating effective dose-rates from environmental radionuclide concentrations. Failure to do so may lead to serious systematic errors in the effective alpha contribution to environmental dose-rates and consequently in age estimates. (author)

  5. Volumetric determination of methanol in ammonium uranil carbonate of nuclear purity

    International Nuclear Information System (INIS)

    Lorenzatto, R.L.

    1989-01-01

    The method developed allows to determine methanol in ammonium uranil carbonate (AUC) from a concentration of 0.01 % with great accuracy. The ammonium uranil carbonate is dissolved in pre-established volumes of a potassium dichromate and concentrated sulfuric acid standardized solution. Instantaneously, the methanol presents oxidates at formic acid, reducing an equivalent amount of dichromate. The remaining dichromate still present, is reduced by adding in excess a standardized solution of ferrous sulphate. The titration of this excess with a standardized solution of potassium permanganate, using ferrous o- phenanthroline as indicator, will give a net and sensitive final point which allows to obtain by a simple estimate the percentage of methanol in the analyzed sample with great precision. Besides, essays are included which were carried out with the aim of proving and putting into evidence in a practical way that the high volatility of the methanol contained in an ammonium uranil carbonate will be the main disadvantage causing errors in defect. Observations for those requesting these analyses and for analysts performing them are mentioned in order to minimize the error factor abovementioned. (Author) [es

  6. Determination of long-lived radionuclide (10Be, 41Ca, 129I) concentrations in nuclear waste by accelerator mass spectrometry

    International Nuclear Information System (INIS)

    Nottoli, Emmanuelle; Bienvenu, Philippe; Labet, Alexandre; Bertaux, Maite; Bourles, Didier; Arnold, Maurice

    2013-01-01

    Radiological characterization of nuclear waste is essential for storage sites management. However, most of Long-Lived Radionuclides (LLRN), important for long-term management, are difficult to measure since concentration levels are very low and waste matrices generally complex. In an industrial approach, LLRN concentrations are not directly measured in waste samples but assessed from scaling factors with respect to easily measured gamma emitters. Ideally, the key nuclide chosen ( 60 Co, 137 Cs) should be produced by a similar mechanism (fission or activation) as the LLRN of interest and should have similar physicochemical properties. However, the uncertainty on the scaling factors, determined from experimental and/or calculation data, can be quite important. Consequently, studies are performed to develop analytical procedures which would lead to determine precisely the concentration of LLRN in nuclear waste. In this context, the aim of this study was to determine the concentrations of three LLRN: 129 I (T 1/2 = 15.7*10 6 a), 41 Ca (T 1/2 = 9.94*10 4 a) and 10 Be (T 1/2 = 1.387*10 6 a) in spent resins used for primary fluid purification in Pressurized Water Reactors using Accelerator Mass Spectrometry (AMS) for measurement. The AMS technique combined mass spectrometry and nuclear physics to achieve highly efficient molecular and elemental isobars separation. Energies of several Million Electron-Volt transferred to the ions in the first accelerating part of specifically developed tandem accelerators lead to molecular isobars destruction through interaction with the argon gas used to strip the injected negative ions to positive ones. At the exit of the tandem accelerator, the energy acquired in both accelerating parts allows an elemental isobars separation based on their significantly different energy loss (dE) while passing through a thickness of matter dx that is proportional to their atomic number (Z) and inversely proportional to ions velocity (v) according to the

  7. Nuclear magnetic resonance line-shape analysis and determination of exchange rates

    International Nuclear Information System (INIS)

    Rao, B.D.

    1989-01-01

    The fact that chemical exchange processes occur at rates that cover a broad range and produce readily detectable effects on the spectrum is one of the attractive features of high-resolution NMR. The description of these line shapes in the presence of spin-spin coupling requires the density matrix theory which is rather complex. Analysis of the line shapes usually needs computer simulations and is capable of providing reliable information on the exchange rates as well as spectral parameters in the absence of exchange. Simplified procedures, ignoring spin-spin coupling, often result in deviations in these exchange and spectral parameters determined. A step-by-step procedure is detailed in this chapter for setting up the matrices required for computing the line shapes of exchanges involving weakly coupled spin systems on the basis of the density matrix theory without the need for a detailed understanding of the theory. A knowledge of the energy level structure and allowed transitions in the NMR spectra of the individual weakly coupled spin systems is all that is required. The procedure is amenable to numerical computation. The group of illustrative examples chosen to demonstrate the development of the computational tools cover some of the commonly encountered cases of exchange from simple systems to rather complex ones. Such exchanges occur frequently in biological molecules, especially those involving enzyme-substrate complexes. In cases where the experimental line shapes are obtained with respectable precision, and the relevant exchange processes are unambiguously identifiable, the computer simulation method of line-shape analysis is capable of providing useful and incisive information. The example of the 31P exchanges in the adenylate kinase is illustrative of this point

  8. Determination of avermectins by the internal standard recovery correction - high performance liquid chromatography - quantitative Nuclear Magnetic Resonance method.

    Science.gov (United States)

    Zhang, Wei; Huang, Ting; Li, Hongmei; Dai, Xinhua; Quan, Can; He, Yajuan

    2017-09-01

    Quantitative Nuclear Magnetic Resonance (qNMR) is widely used to determine the purity of organic compounds. For the compounds with lower purity especially molecular weight more than 500, qNMR is at risk of error for the purity, because the impurity peaks are likely to be incompletely separated from the peak of major component. In this study, an offline ISRC-HPLC-qNMR (internal standard recovery correction - high performance liquid chromatography - qNMR) was developed to overcome this problem. It is accurate by excluding the influence of impurity; it is low-cost by using common mobile phase; and it extends the applicable scope of qNMR. In this method, a mix solution of the sample and an internal standard was separated by HPLC with common mobile phases, and only the eluents of the analyte and the internal standard were collected in the same tube. After evaporation and re-dissolution, it was determined by qNMR. A recovery correction factor was determined by comparison of the solutions before and after these procedures. After correction, the mass fraction of analyte was constant and it was accurate and precise, even though the sample loss varied during these procedures, or even in bad resolution of HPLC. Avermectin B 1 a with the purity of ~93% and the molecular weight of 873 was analyzed. Moreover, the homologues of avermectin B 1 a were determined based on the identification and quantitative analysis by tandem mass spectrometry and HPLC, and the results were consistent with the results of traditional mass balance method. The result showed that the method could be widely used for the organic compounds, and could further promote qNMR to become a primary method in the international metrological systems. Copyright © 2017 Elsevier B.V. All rights reserved.

  9. Determination of nitrogen in wheat flour through Activation analysis using Fast neutron flux of a Thermal nuclear reactor; Determinacion de nitrogeno en harina de trigo mediante analisis por activacion empleando el flujo de neutrones rapidos de un reactor nuclear termico

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, T

    1976-07-01

    In this work is done a technical study for determining Nitrogen (protein) and other elements in wheat flour Activation analysis, with Fast neutrons from a Thermal nuclear reactor. Initially it is given an introduction about the basic principles of the methods of analysis. Equipment used in Activation analysis and a brief description of the neutron source (Thermal nuclear reactor). The realized experiments for determining the flux form in the irradiation site, the half life of N-13 and the interferences due to the sample composition are included too. Finally, the obtained results by Activation and the Kjeldahl method are tabulated. (Author)

  10. Quality assurance program for determining the radioactivity in environmental samples at the Institute of Nuclear Energy Research in Taiwan

    International Nuclear Information System (INIS)

    Gone, J.K.; Wang, T.W.

    2000-01-01

    Interest in determining radioactivity in environmental samples has increased considerably in recent years after the Chernobyl accident in 1986. Environmental monitoring programs have been set up in different countries to measure the trace amount of radionuclides in the environment, and quality of the analytical results on these samples is important because the regulation and safety concerns. A good quality assurance program is essential to provide accurate information for the regulatory body and environmentalists to set proper reactions to protect the environment, and a good analytical result is also important for scientists to determine the transfer of radionuclides between environmental matrices. The Institute of Nuclear Energy Research (lNER) in Taiwan has been working on radionuclide analysis in environmental samples for years, and it's environmental media radioanalytical laboratory (EMRAL) has recently upgraded its quality assurance program for the international standard ISO/lEC guide 25 requirements. The general requirements of lSO/lEC guide 25 has been adapted by the Chinese National Laboratory Accreditation (CNLA) of Taiwan, and CNLA is also a member of International Laboratory Accreditation Cooperation (ILAC) and Asia Pacific Laboratory Accreditation Cooperation (APLAC). This paper summarizes the quality assurance program of lNER's EMRAL. It covers both management and technical sections. These sections have ensured the quality of INER's EMRAL, and they can be applied to different laboratories in the future. (author)

  11. Quality assurance program for determining the radioactivity in environmental samples at the Institute of Nuclear Energy Research in Taiwan

    Energy Technology Data Exchange (ETDEWEB)

    Gone, J.K. [TRR-II Project Team, Institute of Nuclear Energy Research, Taoyuan, Taiwan (China); Wang, T.W. [Division of Health Physics, Institute of Nuclear Energy Research, Taoyuan, Taiwan (China)

    2000-05-01

    Interest in determining radioactivity in environmental samples has increased considerably in recent years after the Chernobyl accident in 1986. Environmental monitoring programs have been set up in different countries to measure the trace amount of radionuclides in the environment, and quality of the analytical results on these samples is important because the regulation and safety concerns. A good quality assurance program is essential to provide accurate information for the regulatory body and environmentalists to set proper reactions to protect the environment, and a good analytical result is also important for scientists to determine the transfer of radionuclides between environmental matrices. The Institute of Nuclear Energy Research (lNER) in Taiwan has been working on radionuclide analysis in environmental samples for years, and it's environmental media radioanalytical laboratory (EMRAL) has recently upgraded its quality assurance program for the international standard ISO/lEC guide 25 requirements. The general requirements of lSO/lEC guide 25 has been adapted by the Chinese National Laboratory Accreditation (CNLA) of Taiwan, and CNLA is also a member of International Laboratory Accreditation Cooperation (ILAC) and Asia Pacific Laboratory Accreditation Cooperation (APLAC). This paper summarizes the quality assurance program of lNER's EMRAL. It covers both management and technical sections. These sections have ensured the quality of INER's EMRAL, and they can be applied to different laboratories in the future. (author)

  12. Determination of the subcadmium flux in the Triga Mark III reactor of the Nuclear Center in Mexico

    International Nuclear Information System (INIS)

    Rodiguez V, F.J.

    1975-01-01

    The determination of the subcadmium flux profile (neutrons with energy between 0 and 0.4 eV approximatley) in the core of the reactor Triga Mark III in the Nuclear Center of Mexico was made. The technique used for that purpose consists in placing alternativelly indium sheets covered and uncovered with cadmium and separated by fragments of aluminium 2.54cm wide in an aluminium tube whose external diameter reaches 0.635cm. This tube is introduced in each of the 21 axial irradiation places of the sheets the activity of gamma rays of 1.293 MeV of In-116m produced during the irradiation, is measured using a monochannel analyzer. We obtain graphs of the specific counting ratio vs position for the sheets uncovered and covered with cadmium; using quadratic interpolation we compute in each position the missing specific measuring ratio. The difference between the specific counting ratios with our cadmium and with cadmium multiplied by a constant gives the subcadmium flux in the z point. For irradiation at 10 watts, 1 Kilowatt and 1 megawatt the results show profiles which in general terms are in accordance with those which were obtained theoretically for a cylyndrical reactor using group theory. The greatest flow given by the manufacturer of the reactor is in the values range obtained experimentally.For the calculations, the method uses a FORTRAN IV program so that the determinations can be made routinely. (author)

  13. Zirconium and Yttrium (p, d) Surrogate Nuclear Reactions: Measurement and determination of gamma-ray probabilities: Experimental Physics Report

    Energy Technology Data Exchange (ETDEWEB)

    Burke, J. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hughes, R. O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Escher, J. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Scielzo, N. D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Casperson, R. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ressler, J. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Saastamoinen, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ota, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Park, H. I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ross, T. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McCleskey, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McCleskey, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Austin, R. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Rapisarda, G. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-21

    This technical report documents the surrogate reaction method and experimental results used to determine the desired neutron induced cross sections of 87Y(n,g) and the known 90Zr(n,g) cross section. This experiment was performed at the STARLiTeR apparatus located at Texas A&M Cyclotron Institute using the K150 Cyclotron which produced a 28.56 MeV proton beam. The proton beam impinged on Y and Zr targets to produce the nuclear reactions 89Y(p,d)88Y and 92Zr(p,d)91Zr. Both particle singles data and particle-gamma ray coincident data were measured during the experiment. This data was used to determine the γ-ray probability as a function of energy for these reactions. The results for the γ-ray probabilities as a function of energy for both these nuclei are documented here. For completeness, extensive tabulated and graphical results are provided in the appendices.

  14. Accurate determination of 129I concentrations and 129I/137Cs ratios in spent nuclear resins by Accelerator Mass Spectrometry

    International Nuclear Information System (INIS)

    Nottoli, Emmanuelle; Bienvenu, Philippe; Labet, Alexandre; Bourlès, Didier; Arnold, Maurice; Bertaux, Maité

    2014-01-01

    Determining long-lived radionuclide concentrations in radioactive waste has fundamental implications for the long-term management of storage sites. This paper focuses on the measurement of low 129 I contents in ion exchange resins used for primary fluid purification in Pressurised Water Reactors (PWR). Iodine-129 concentrations were successfully determined using Accelerator Mass Spectrometry (AMS) following a chemical procedure which included (1) acid digestion of resin samples in HNO 3 /HClO 4 , (2) radioactive decontamination by selective iodine extraction using a new chromatographic resin (CL Resin), and (3) AgI precipitation. Measured 129 I concentrations ranged from 4 to 12 ng/g, i.e. from 0.03 to 0.08 Bq/g. The calculation of 129 I/ 137 Cs activity ratios used for routine waste management produced values in agreement with the few available data for PWR resin samples. - Highlights: • In the context of radioactive waste management, this study aimed at measuring 129 I in spent resins using accelerator mass spectrometry. • The treatment procedure included microwave acid digestion of samples, iodine extraction by CL resins and AgI precipitation. • Developed first on synthetic matrices, the chemical treatment procedure was then successfully applied to real resin samples. • 129 I concentrations ranged from 4 to 12 ng/g of dry resin. • Results are in agreement with previous measurements and support reference values currently used for nuclear resin management

  15. Determination of ethylenediaminetetraacetic acid in nuclear waste by high-performance liquid chromatography coupled with electrospray mass spectrometry.

    Science.gov (United States)

    du Bois de Maquillé, Laurence; Renaudin, Laetitia; Goutelard, Florence; Jardy, Alain; Vial, Jérôme; Thiébaut, Didier

    2013-02-08

    EDTA is a chelating agent that has been used in decontamination processes. Its quantification is required for nuclear waste management because it affects the mobility of radionuclides and metals in environment and, thus, can harm the safety of the storage. Ion-pair chromatography coupled with electrospray mass spectrometry detection is a convenient method for quantitative analysis of EDTA but EDTA should be present as a single anionic chelate form. However, radioactive liquid wastes contain high concentrations of heavy metals and salts and consequently, EDTA is present as several chelates. Speciation studies were carried out to choose a metal cation to be added in excess to the solution to obtain a major chelate form. Fe is the predominant cation and Fe(III)-EDTA is thermodynamically favored but these speciation studies showed that ferric hydroxide precipitated above pH 2. Consequently, it was not possible to quantify EDTA as Fe(III)-EDTA complex. Therefore, Ni(2+) was chosen but its use implied pretreatment with a base of the solution to eliminate Fe. Deuterated EDTA was used as tracer in order to validate the whole procedure, from the treatment with a base to the final analysis by HPLC-ESI-MS. This analytical method was successfully applied for EDTA quantification in two real effluents resulting from a nuclear liquid waste process. A recovery rate between 60 and 80% was obtained. The limit of detection of this method was determined at 34×10(-9)mol L(-1). Copyright © 2012 Elsevier B.V. All rights reserved.

  16. Determination of the standards of the thermo-physiological tolerance for working in basic nuclear installation in TIVA protective clothing

    International Nuclear Information System (INIS)

    Casanova, P.; Daret, J.L.; Besnard, Y.; Clerc, N.; Savourey, G.; Launay, J.C.

    2011-01-01

    The purpose of this study was to determine the duration limited exposure (DLE) for working in a contaminated zone in a basic nuclear installation using the new ventilated TIVA protective clothing. Five subjects underwent a treadmill exercise (3.5 km/h, 3% of slope) of up to 2 h in a climatic chamber at 25, 35, and 45 deg. C. Cardiac frequency, rectal temperature and skin temperature were continuously recorded. The dehydration level was measured by the loss of weight during the exercise. At 25 deg. C, thermal and cardiovascular thresholds are not reached; the risk is dehydration if the exercise is prolonged. In contrast, the thresholds for Tre at 39 deg. C (97 ± 29 and 69 ± 28 min for 35 and 45 deg. C, respectively) and for the increase in Tre (+1.5 deg. C) are reached earlier (84 ± 38 min and 57 ± 21 min at 35 and 45 deg. C, respectively). This leads to a higher heat storage (42.2 ± 22.9 W/m 2 and 63.7 ± 29.4 W/m 2 , at 35 and 45 deg. C, respectively), which constitutes a higher risk of heat illnesses. The dehydration level is 2% of the weight for the tests at 35 and 45 deg. C. As a consequence, DLE for working in a contaminated zone in a basic nuclear installation in environmental conditions and using the new ventilated TIVA protective clothing, as encountered in our experiments, are proposed to avoid hyperthermic accidents. (authors)

  17. The use of isotopic correlation technique for determination of sup(241)Am and sup(243)Am concentration in nuclear irradiated fuels

    International Nuclear Information System (INIS)

    Souza Sarkis, J.E. de.

    1990-01-01

    In the last years the isotopic correlation technique is emerging as a powerful tool for the determination of concentration and isotopic composition of heavy nuclides in the nuclear fuel cycle. Accordingly, this technique has gained significant importance for the safeguard of the nuclear materials as well as for the accounting and build up of actinides elements in the irradiated nuclear fuels. In this work 42 isotopic correlations between the nuclides sup(241)Am and sup(243)Am and post irradiation isotopic data of 7 samples from fuel element BE-124 and 1 sample from fuel element BE-120 from the Obrigheim pressurized water nuclear power reactor, Federal Republic of Germany, were proposed. These isotopic correlations allowed to estimate the isotopic concentrations of sup(241)Am and sup(243)Am with an average deviation, relative to the experimental data obtained from isotopic dilution mass spectrometry technique, of 10%. These results are more precise than those found using the computer code ORIGEN 2 demonstrating the great potential of this technique for the determination of isotopic concentration and build up of those nuclides in irradiated nuclear fuels. The analytical and other experimental aspects of the post irradiation isotopic analysis of nuclear fuels are also discussed. (author)

  18. Oxygen determination in materials by {sup 18}O(p,αγ){sup 15}N nuclear reaction

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, Sanjiv, E-mail: sanjucccm@rediffmail.com [National Centre for Compositional Characterization of Materials, BARC, ECIL Post, Hyderabad 500062 (India); Sunitha, Y.; Reddy, G.L.N.; Sukumar, A.A.; Ramana, J.V.; Sarkar, A. [National Centre for Compositional Characterization of Materials, BARC, ECIL Post, Hyderabad 500062 (India); Verma, Rakesh [Analytical Chemistry Division, BARC, Mumbai 400085 (India)

    2016-07-01

    The paper presents a proton induced γ-ray emission method based on {sup 18}O(p,αγ){sup 15}N nuclear reaction to determine bulk oxygen in materials. The determination involves the measurement of 5.27 MeV γ-rays emitted following the de-excitation of {sup 15}N nuclei. A description of the energetics of the reaction is given to provide an insight into the origin of 5.27 MeV γ-rays. In addition, thick target γ-ray yields and the limits of detection are measured to ascertain the analytical potential of the reaction. The thick-target γ-ray yields are measured with a high purity germanium detector and a bismuth germanate detector at 0° as well as 90° angles in 3.0–4.2 MeV proton energy region. The best limit of detection of about 1.3 at.% is achieved at 4.2 MeV proton energy for measurements at 0° as well 90° angles with the bismuth germanate detector while the uncertainty in quantitative analysis is <8%. The reaction has a probing depth of several tens of microns. Interferences can arise from fluorine due to the occurrence of {sup 19}F(p,αγ){sup 16}O reaction that emits 6–7 MeV γ-rays. The analytical potential of the methodology is demonstrated by determining oxygen in several oxide as well as non-oxide materials.

  19. Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 4: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, slow bubbling rate

    International Nuclear Information System (INIS)

    2008-01-01

    ISO 18213 deals with the acquisition, standardization, analysis, and use of calibration to determine liquid volumes in process tanks for the accountancy of nuclear materials. This part of ISO 18213 is complementary to the other parts, ISO 18213-1 (procedural overview), ISO 18213-2 (data standardization), ISO 18213-3 (statistical methods), ISO 18213-5 (fast bubbling rate) and ISO 18213-6 (in-tank determination of liquid density). The procedure presented herein for determining liquid height from measurements of induced pressure applies specifically when a very slow bubbling rate is employed. A similar procedure that is appropriate for a fast bubbling rate is given in ISO 18213-5. Measurements of the volume and height of liquid in a process accountancy tank are often made in order to estimate or verify the tank's calibration or volume measurement equation. The calibration equation relates the response of the tank's measurement system to some independent measure of tank volume. Beginning with an empty tank, calibration data are typically acquired by introducing a series of carefully measured quantities of some calibration liquid into the tank. The quantity of liquid added, the response of the tank's measurement system, and relevant ambient conditions such as temperature are measured for each incremental addition. Several calibration runs are made to obtain data for estimating or verifying a tank's calibration or measurement equation. A procedural overview of the tank calibration and volume measurement process is given in ISO 18213-1. An algorithm for standardizing tank calibration and volume measurement data to minimize the effects of variability in ambient conditions that prevail during the measurement period is given in ISO 18213-2. The procedure presented in this part of ISO 18213 for determining the height of calibration liquid in the tank from a measurement of the pressure it induces in the tank's measurement system is a vital component of that algorithm. In some

  20. Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 5: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, fast bubbling rate

    International Nuclear Information System (INIS)

    2008-01-01

    ISO 18213 deals with the acquisition, standardization, analysis, and use of calibration to determine liquid volumes in process tanks for the accountancy of nuclear materials. This part of ISO 18213 is complementary to the other parts, ISO 18213-1 (procedural overview), ISO 18213-2 (data standardization), ISO 18213-3 (statistical methods), ISO 18213-5 (fast bubbling rate) and ISO 18213-6 (in-tank determination of liquid density). The procedure presented herein for determining liquid height from measurements of induced pressure applies specifically when a very slow bubbling rate is employed. A similar procedure that is appropriate for a fast bubbling rate is given in ISO 18213-5. Measurements of the volume and height of liquid in a process accountancy tank are often made in order to estimate or verify the tank's calibration or volume measurement equation. The calibration equation relates the response of the tank's measurement system to some independent measure of tank volume. Beginning with an empty tank, calibration data are typically acquired by introducing a series of carefully measured quantities of some calibration liquid into the tank. The quantity of liquid added, the response of the tank's measurement system, and relevant ambient conditions such as temperature are measured for each incremental addition. Several calibration runs are made to obtain data for estimating or verifying a tank's calibration or measurement equation. A procedural overview of the tank calibration and volume measurement process is given in ISO 18213-1. An algorithm for standardizing tank calibration and volume measurement data to minimize the effects of variability in ambient conditions that prevail during the measurement period is given in ISO 18213-2. The procedure presented in this part of ISO 18213 for determining the height of calibration liquid in the tank from a measurement of the pressure it induces in the tank's measurement system is a vital component of that algorithm. In some