Childhood cancer and nuclear power plants in Switzerland: a census-based cohort study.

BACKGROUND: Previous studies on childhood cancer and nuclear power plants (NPPs) produced conflicting results. We used a cohort approach to examine whether residence near NPPs was associated with leukaemia or any childhood cancer in Switzerland. METHODS: We computed person-years at risk for children aged 0-15 years born in Switzerland from 1985 to 2009, based on the Swiss censuses 1990 and 2000 and identified cancer cases from the Swiss Childhood Cancer Registry. We geo-coded place of residence at birth and calculated incidence rate ratios (IRRs) with 95% confidence intervals (CIs) comparing the risk of cancer in children born <5 km, 5-10 km and 10-15 km from the nearest NPP with children born >15 km away, using Poisson regression models. RESULTS: We included 2925 children diagnosed with cancer during 21 117 524 person-years of follow-up; 953 (32.6%) had leukaemia. Eight and 12 children diagnosed with leukaemia at ages 0-4 and 0-15 years, and 18 and 31 children diagnosed with any cancer were born <5 km from a NPP. Compared with children born >15 km away, the IRRs (95% CI) for leukaemia in 0-4 and 0-15 year olds were 1.20 (0.60-2.41) and 1.05 (0.60-1.86), respectively. For any cancer, corresponding IRRs were 0.97 (0.61-1.54) and 0.89 (0.63-1.27). There was no evidence of a dose-response relationship with distance (P > 0.30). Results were similar for residence at diagnosis and at birth, and when adjusted for potential confounders. Results from sensitivity analyses were consistent with main results. CONCLUSIONS: This nationwide cohort study found little evidence of an association between residence near NPPs and the risk of leukaemia or any childhood cancer.

Características de tolerância à seca em genótipos de uma coleção nuclear de arroz de terras altas

Resumo:O objetivo deste trabalho foi avaliar características morfofisiológicas relacionadas à tolerância ao estresse hídrico em genótipos de uma coleção nuclear temática de arroz de terras altas, bem como identificar os materiais mais tolerantes. Foram avaliados 100 genótipos de arroz de terras altas em experimentos conduzidos com e sem estresse por deficiência hídrica. Os genótipos tenderam a aumentar o número de dias para o florescimento (FLO) e a diminuir a altura (ALT), na condição de estresse, mas manifestaram ampla variação de comportamento. A esterilidade das espiguetas (EST) foi a característica mais importante para a seleção, nas duas condições de cultivo, em razão de sua elevada correlação negativa com a produtividade. O número de perfilhos não diferiu entre os genótipos na condição sem estresse, mas houve diferença significativa sob estresse hídrico. Os genótipos Ligeiro e Canela de Ferro apresentaram baixos índices de susceptibilidade à seca (ISS), mas baixa produtividade em ambas as condições de cultivo; já os materiais Catetão, Jatobá e Arroz do Maranhão apresentaram elevada produtividade sob estresse e valores de ISS relativamente baixos. EST, FLO, ALT e ISS são características morfofisiológicas relacionadas à tolerância à seca, e os genótipos Catetão, Jatobá e Arroz do Maranhão podem constituir boas fontes de genes para tolerância à seca em programas de melhoramento.

Guiding ligands to nuclear receptors.

Retinoic acid-the active metabolite of vitamin A-influences biological processes by activating the retinoic acid receptor (RAR). In this issue, Schug et al. (2007) demonstrate that retinoic acid also activates the peroxisome proliferator-activated receptor beta/delta (PPARbeta/delta). Remarkably, retinoic acid signaling through RAR or PPARbeta/delta-which depends on cytoplasmic retinoic acid transporters-commits the cell to opposite fates, apoptosis or survival, respectively.

Plasmapolttoprosessin kehittäminen ja optimointi

Ydinvoimaloidenprimaarivesikierron puhdistukseen käytetään ioninvaihtohartsia. Käytönjälkeen ioninvaihtohartsi luokitellaan matalaja keskiaktiivisiin jätteisiin. Plasmakäsittelyllä käytetyn ioninvaihtohartsin tilavuutta voidaan pienentää sekä sen orgaaninen luonne poistaa. Plasmakäsittelyn tarkoituksena on hapettaa orgaaninen aines oksideiksi, jotka poistuvat prosessista savukaasuina. Epäorgaaninen aines, joka sisältää radioaktiivisen aineksen, on tarkoitus hapettaa oksideiksi ja sulfideiksi, jotka voidaan kerätä talteen tuhkana. Tässä diplomityössä käsitellään käytetyn ioninvaihtohartsin käsittelyyn suunnitellun plasmapolttoprosessin kehittämistä ja optimointia. Ioninvaihtohartsin plasmakäsittelyssä syntyvien reaktiotuotteiden selvittäminen suoritettiin tarkastelemalla ainetaseita sekä aihetta käsitteleviä tutkimuksia. Näiden perusteella parannettiin jäähdytystä, suunniteltiin jatkuvatoiminen syöttömenetelmä sekä laadittiin toimintaalueen reunaehdot laitteistolle. Koelaitteistossa 6,5 kW:n rfteho syötetään sovitinpiirin ja kuparisen induktiokelan kautta plasmaan. Plasmakaasuna on käytetty hapenja argonin seoskaasua. Plasmapolttoa on seurattu massaspektrometrilla, optisella emissiospektrometrilla, lämpösekä painemittareilla. Laskennan ja kokeiden pohjalta selvitettiin optimaalinen seossuhde plasmakaasulle, paineen ja tehon noston vaikutus hartsin polttonopeuteen sekä jatkuvatoimisen syöttömenetelmän edut panostoimiseen syöttöön. Rfgeneraattorin teho rajoitti jatkuvatoimisen polttonopeuden 130 g/h ja hetkellisen polttonopeuden 175 g/h. Radioaktiivisten aineiden pidätys oli 93,5 % cesiumin osalta. Tulosten perusteella 4 kg/h ioninvaihtohartsia polttavan laitteiston tehon lähteeksi tarvitaan 65 kW rfgeneraattori. Palamattoman hartsin ja tuhkan kulkeutuminen partikkelisuodattimille sekä reaktiotuotteena syntyvien rikinoksidien käsittely vaatii vielä jatkotutkimusta.

Käytetyn ydinpolttoaineen kapselointilaitoksessa muodostuvat radioaktiiviset jätteet

Tässä työssä ontarkasteltu käytetyn ydinpolttoaineen kapselointilaitoksessa muodostuvia radioaktiivisia jätteitä. Kapselointilaitos rakennetaan Olkiluotoon joko Olkiluodon ydinvoimalaitoksen käytetyn ydinpolttoaineen välivaraston yhteyteen tai loppusijoituslaitokseen kytkettynä laitoksena. Työssä on otettu huomioon molemmat vaihtoehdot ja niiden eroavaisuudet prosessien ja jätemäärien osilta. Kaikki jäte, joka muodostuu kapselointilaitoksen valvonta-alueella, luokitellaan radioaktiiviseksi jätteeksi. Radioaktiivisia jätteitä muodostuu, kun käytetystä ydinpolttoaineesta irronneet radioaktiiviset aineet kontaminoivat laitoksen rakenteita ja laitteita. Muodostuvat radioaktiiviset jätteet kiinteytetään ja sijoitetaan loppusijoitustilan yhteyteen rakennettavaan käyttö- ja käytöstäpoisto-jäteluolaan. Hyvin vähäaktiivinen jäte voidaan vapauttaa valvonnasta aktiivisuusmittauksen jälkeen. Radioaktiivisia jätteitä muodostuu kapselointilaitoksen toiminnan aikana vähäisiä määriä verrattuna ydinvoimalaitoksiin. Vertailtaessa molempien kapselointilaitosvaihtoehtojen radioaktiivisten jätteiden määriä, ainoastaan loppusijoitettavan nestemäisten jätteiden määrässä on eroa.

Modelling of a Hydrogen Catalytic Recombiner for Nuclear Power Plant Containment Studies; Case: Siemens FR90/1-150 Recombiner in TONUS OD Code

Ydinvoimalaitokset on suunniteltu ja rakennettu niin, että niillä on kyky selviytyä erilaisista käyttöhäiriöistä ja onnettomuuksista ilman laitoksen vahingoittumista sekä väestön ja ympäristön vaarantumista. On erittäin epätodennäköistä, että ydinvoimalaitosonnettomuus etenee reaktorisydämen vaurioitumiseen asti, minkä seurauksena sydänmateriaalien hapettuminen voi tuottaa vetyä. Jäädytyspiirin rikkoutumisen myötä vety saattaa kulkeutua ydinvoimalaitoksen suojarakennukseen, jossa se voi muodostaa palavan seoksen ilman hapen kanssa ja palaa tai jopa räjähtää. Vetypalosta aiheutuvat lämpötila- ja painekuormitukset vaarantavat suojarakennuksen eheyden ja suojarakennuksen sisällä olevien turvajärjestelmien toimivuuden, joten tehokas ja luotettava vedynhallintajärjestelmä on tarpeellinen. Passiivisia autokatalyyttisiä vetyrekombinaattoreita käytetäänyhä useammissa Euroopan ydinvoimaitoksissa vedynhallintaan. Nämä rekombinaattorit poistavat vetyä katalyyttisellä reaktiolla vedyn reagoidessa katalyytin pinnalla hapen kanssa muodostaen vesihöyryä. Rekombinaattorit ovat täysin passiivisiaeivätkä tarvitse ulkoista energiaa tai operaattoritoimintaa käynnistyäkseen taitoimiakseen. Rekombinaattoreiden käyttäytymisen tutkimisellatähdätään niiden toimivuuden selvittämiseen kaikissa mahdollisissa onnettomuustilanteissa, niiden suunnittelun optimoimiseen sekä niiden optimaalisen lukumäärän ja sijainnin määrittämiseen suojarakennuksessa. Suojarakennuksen mallintamiseen käytetään joko keskiarvoistavia ohjelmia (Lumped parameter (LP) code), moniulotteisia virtausmalliohjelmia (Computational Fluid Dynamics, CFD) tai näiden yhdistelmiä. Rekombinaattoreiden mallintaminen on toteutettu näissä ohjelmissa joko kokeellisella, teoreettisella tai yleisellä (eng. Global Approach) mallilla. Tämä diplomityö sisältää tulokset TONUS OD-ohjelman sisältämän Siemens FR90/1-150 rekombinaattorin mallin vedynkulutuksen tarkistuslaskuista ja TONUS OD-ohjelmalla suoritettujen laskujen tulokset Siemens rekombinaattoreiden vuorovaikutuksista. TONUS on CEA:n (Commissariat à 1'En¬ergie Atomique) kehittämä LP (OD) ja CFD -vetyanalyysiohjelma, jota käytetään vedyn jakautumisen, palamisenja detonaation mallintamiseen. TONUS:sta käytetään myös vedynpoiston mallintamiseen passiivisilla autokatalyyttisillä rekombinaattoreilla. Vedynkulutukseen vaikuttavat tekijät eroteltiin ja tutkittiin yksi kerrallaan. Rekombinaattoreiden vuorovaikutuksia tutkittaessa samaan tilavuuteen sijoitettiin eri kokoisia ja eri lukumäärä rekombinaattoreita. Siemens rekombinaattorimalli TONUS OD-ohjelmassa laskee vedynkulutuksen kuten oletettiin ja tulokset vahvistavat TONUS OD-ohjelman fysikaalisen laskennan luotettavuuden. Mahdollisia paikallisia jakautumia tutkitussa tilavuudessa ei voitu havaita LP-ohjelmalla, koska se käyttäälaskennassa suureiden tilavuuskeskiarvoja. Paikallisten jakautumien tutkintaan tarvitaan CFD -laskentaohjelma.

Procés de patrimonialització cultural de la central nuclear de Lemoiz (Bizkaia)

El propòsit central d’aquest treball és el de plantejar un procés d’activació del patrimoni cultural i històric, concretament el de la Central Nuclear de Lemoiz (Biscaia). Si la central fos declarada patrimoni industrial i històric es podria establir un punt de partida per a la resolució d’una situació complexa a nivell social, polític, urbanístic i medi-ambiental com és l’existència de la central nuclear

In vivo nuclear translocation of mineralocorticoid and glucocorticoid receptors in rat kidney: differential effect of corticosteroids along the distal tubule.

Aldosterone and corticosterone bind to mineralocorticoid (MR) and glucocorticoid receptors (GR), which, upon ligand binding, are thought to translocate to the cell nucleus to act as transcription factors. Mineralocorticoid selectivity is achieved by the 11β-hydroxysteroid dehydrogenase type 2 (11β-HSD2) that inactivates 11β-hydroxy glucocorticoids. High expression levels of 11β-HSD2 characterize the aldosterone-sensitive distal nephron (ASDN), which comprises the segment-specific cells of late distal convoluted tubule (DCT2), connecting tubule (CNT), and collecting duct (CD). We used MR- and GR-specific antibodies to study localization and regulation of MR and GR in kidneys of rats with altered plasma aldosterone and corticosterone levels. In control rats, MR and GR were found in cell nuclei of thick ascending limb (TAL), DCT, CNT, CD cells, and intercalated cells (IC). GR was also abundant in cell nuclei and the subapical compartment of proximal tubule (PT) cells. Dietary NaCl loading, which lowers plasma aldosterone, caused a selective removal of GR from cell nuclei of 11β-HSD2-positive ASDN. The nuclear localization of MR was unaffected. Adrenalectomy (ADX) resulted in removal of MR and GR from the cell nuclei of all epithelial cells. Aldosterone replacement rapidly relocated the receptors in the cell nuclei. In ASDN cells, low-dose corticosterone replacement caused nuclear localization of MR, but not of GR. The GR was redistributed to the nucleus only in PT, TAL, early DCT, and IC that express no or very little 11β-HSD2. In ASDN cells, nuclear GR localization was only achieved when corticosterone was replaced at high doses. Thus ligand-induced nuclear translocation of MR and GR are part of MR and GR regulation in the kidney and show remarkable segment- and cell type-specific characteristics. Differential regulation of MR and GR may alter the level of heterodimerization of the receptors and hence may contribute to the complexity of corticosteroid effects on ASDN function.

Aplicações da tomografia de ressonância magnética nuclear como método não-destrutivo para avaliar os efeitos de injúrias mecânicas em goiabas 'Paluma' e 'Pedro Sato'

Objetivou-se determinar o potencial do uso da tomografia de ressonância magnética, como método não-destrutivo, para avaliar os efeitos das injúrias mecânicas em goiabas. Foram utilizados frutos no estádio de maturação "de vez" das cultivares Paluma e Pedro Sato. Na injúria por impacto, os frutos foram deixados cair, em queda livre, de uma altura de 1,20 m, sofrendo dois impactos, em lados opostos de sua porção equatorial. Na injúria por compressão, os frutos foram submetidos a um peso de 29,4 N, por 15 minutos. Para a injúria por corte, foram efetuados dois cortes, no sentido longitudinal dos frutos, de exatamente 30 mm de comprimento por 2 mm de profundidade. Os frutos injuriados foram armazenados sob condições de ambiente (22 ± 2 °C e 40 %UR). Foram realizadas análises com tomógrafo de ressonância magnética Varian Inova de 2 Tesla. As imagens foram obtidas a partir da detecção dos prótons de hidrogênio (¹H). Para cada fruto, foram obtidos tomogramas simétricos a partir do centro do fruto. A tomografia de ressonância magnética nuclear mostrou-se uma ferramenta eficaz na detecção de injúrias internas de frutos. O estresse físico causado pelo impacto produziu um colapso interno nos lóculos desses frutos (internal bruising), levando à perda da integridade celular e a conseqüente liquefação dos tecidos placentários. A cultivar Pedro Sato mostrou uma suscetibilidade maior à injúria por impacto que a 'Paluma'. A injúria por compressão tornou-se mais evidente no pericarpo externo do fruto, de ambas as cultivares. A injúria por corte levou a lignificação dos tecidos no local injuriado e deformações superficiais devido à perda acentuada de matéria fresca no local da lesão, evidentes no sexto dia de avaliação.

Different concentrations of Mg++ ions affect nuclear matrix protein distribution during thermal stabilization of isolated nuclei.

The nuclear matrix, a proteinaceous network believed to be a scaffolding structure determining higher-order organization of chromatin, is usually prepared from intact nuclei by a series of extraction steps. In most cell types investigated the nuclear matrix does not spontaneously resist these treatments but must be stabilized before the application of extracting agents. Incubation of isolated nuclei at 37C or 42C in buffers containing Mg++ has been widely employed as stabilizing agent. We have previously demonstrated that heat treatment induces changes in the distribution of three nuclear scaffold proteins in nuclei prepared in the absence of Mg++ ions. We studied whether different concentrations of Mg++ (2.0-5 mM) affect the spatial distribution of nuclear matrix proteins in nuclei isolated from K562 erythroleukemia cells and stabilized by heat at either 37C or 42C. Five proteins were studied, two of which were RNA metabolism-related proteins (a 105-kD component of splicing complexes and an RNP component), one a 126-kD constituent of a class of nuclear bodies, and two were components of the inner matrix network. The localization of proteins was determined by immunofluorescent staining and confocal scanning laser microscope. Mg++ induced significant changes of antigen distribution even at the lowest concentration employed, and these modifications were enhanced in parallel with increase in the concentration of the divalent cation. The different sensitivity to heat stabilization and Mg++ of these nuclear proteins might reflect a different degree of association with the nuclear scaffold and can be closely related to their functional or structural role.

Challenges in packaging waste management: A case study in the fast food industry

The main research problem of this thesis is to find out the means of promoting the recovery of packaging waste generated in thefast food industry. The recovery of packaging waste generated in the fast food industry is demanded by the packaging waste legislation and expected by the public. The means are revealed by the general factors influencing the recovery of packaging waste, analysed by a multidisciplinary literature review and a case study focusing on the packaging waste managementof McDonald's Oy operating in Finland. The existing solid waste infrastructure does not promote the recovery ofpackaging waste generated in the fast food industry. The theoretical recovery rate of the packaging waste is high, 93 %, while the actual recovery rate is only 29 % consisting of secondary packaging manufactured from cardboard. The total recovery potential of packaging waste is 64 %, resulting in 1 230 tonnes ofrecoverable packaging waste. The achievable recovery potential of 33 %, equalling 647 tonnes of packaging waste could be recovered, but is not recovered mainly because of non-working waste management practises. The theoretical recovery potential of 31 %, equalling 583 tonnes of packaging waste can not be recovered by the existing solid waste infrastructure because of the obscure status of commecial waste, the improper operation ofproducer organisations, and the municipal autonomy. The sorting experiment indicated that it is possible to reach the achievable recovery potential inthe existing solid waste infrastructure. The achievement is promoted by waste producer -oriented waste management practises. The theoretical recovery potential can be reached by increasing the consistency of the solid waste infrastructure through governmental action.

Validation Studies of Thermal-hydraulic Code for Safety Analysis of Nuclear Power Plants

This thesis gives an overview of the validation process for thermal hydraulic system codes and it presents in more detail the assessment and validation of the French code CATHARE for VVER calculations. Three assessment cases are presented: loop seal clearing, core reflooding and flow in a horizontal steam generator. The experience gained during these assessment and validation calculations has been used to analyze the behavior of the horizontal steam generator and the natural circulation in the geometry of the Loviisa nuclear power plant. The cases presented are not exhaustive, but they give a good overview of the work performed by the personnel of Lappeenranta University of Technology (LUT). Large part of the work has been performed in co-operation with the CATHARE-team in Grenoble, France. The design of a Russian type pressurized water reactor, VVER, differs from that of a Western-type PWR. Most of thermal-hydraulic system codes are validated only for the Western-type PWRs. Thus, the codes should be assessed and validated also for VVER design in order to establish any weaknesses in the models. This information is needed before codes can be used for the safety analysis. Theresults of the assessment and validation calculations presented here show that the CATHARE code can be used also for the thermal-hydraulic safety studies for VVER type plants. However, some areas have been indicated which need to be reassessed after further experimental data become available. These areas are mostly connected to the horizontal stem generators, like condensation and phase separation in primary side tubes. The work presented in this thesis covers a large numberof the phenomena included in the CSNI code validation matrices for small and intermediate leaks and for transients. Also some of the phenomena included in the matrix for large break LOCAs are covered. The matrices for code validation for VVER applications should be used when future experimental programs are planned for code validation.

Effect of Noncondensable Gases on Circulation of Primary Coolant in Nuclear Power Plants in Abnormal Situations

The present study focuses on two effects of the presence of a noncondensable gas on the thermal-hydraulic behavior of thecoolant of the primary circuit of a nuclear reactor in the VVER-440 geometry inabnormal situations. First, steam condensation with the presence of air was studied in the horizontal tubes of the steam generator (SG) of the PACTEL test facility. The French thermal-hydraulic CATHARE code was used to study the heat transfer between the primary and secondary side in conditions derived from preliminary experiments performed by VTT using PACTEL. In natural circulation and single-phase vapor conditions, the injection of a volume of air, equivalent to the totalvolume of the primary side of the SG at the entrance of the hot collector, did not stop the heat transfer from the primary to the secondary side. The calculated results indicate that air is located in the second half-length (from the mid-length of the tubes to the cold collector) in all the tubes of the steam generator The hot collector remained full of steam during the transient. Secondly, the potential release of the nitrogen gas dissolved in the water of the accumulators of the emergency core coolant system of the Loviisa nuclear power plant (NPP) was investigated. The author implemented a model of the dissolution and release ofnitrogen gas in the CATHARE code; the model created by the CATHARE developers. In collaboration with VTT, an analytical experiment was performed with some components of PACTEL to determine, in particular, the value of the release time constant of the nitrogen gas in the depressurization conditions representative of the small and intermediate break transients postulated for the Loviisa NPP. Such transients, with simplified operating procedures, were calculated using the modified CATHARE code for various values of the release time constant used in the dissolution and release model. For the small breaks, nitrogen gas is trapped in thecollectors of the SGs in rather large proportions. There, the levels oscillate until the actuation of the low-pressure injection pumps (LPIS) that refill the primary circuit. In the case of the intermediate breaks, most of the nitrogen gas is expelled at the break and almost no nitrogen gas is trapped in the SGs. In comparison with the cases calculated without taking into account the release of nitrogen gas, the start of the LPIS is delayed by between 1 and 1.75 h. Applicability of the obtained results to the real safety conditions must take into accountthe real operating procedures used in the nuclear power plant.