Allocation of uranium enrichment services to fuel foreign and domestic nuclear reactors, Energy Research and Development Administration, Department of State : report to the Committee on Foreign Affairs, House of Representatives /

Publication date stamped on cover.

International nuclear spent fuel storage programs : hearing before the Subcommittees on International Security and Scientific Affairs and on International Economic Policy and Trade of the Committee on Foreign Affairs, House of Representatives, Ninety-sixth Congress, first session, May 3, 1979.

Mode of access: Internet.

Nuclear energy and world fuel prices.

Bibliographical footnotes.

Nuclear receptor Rev-erb alpha (Nr1d1) functions in concert with Nr2e3 to regulate transcriptional networks in the retina.

The majority of diseases in the retina are caused by genetic mutations affecting the development and function of photoreceptor cells. The transcriptional networks directing these processes are regulated by genes such as nuclear hormone receptors. The nuclear hormone receptor gene Rev-erb alpha/Nr1d1 has been widely studied for its role in the circadian cycle and cell metabolism, however its role in the retina is unknown. In order to understand the role of Rev-erb alpha/Nr1d1 in the retina, we evaluated the effects of loss of Nr1d1 to the developing retina and its co-regulation with the photoreceptor-specific nuclear receptor gene Nr2e3 in the developing and mature retina. Knock-down of Nr1d1 expression in the developing retina results in pan-retinal spotting and reduced retinal function by electroretinogram. Our studies show that NR1D1 protein is co-expressed with NR2E3 in the outer neuroblastic layer of the developing mouse retina. In the adult retina, NR1D1 is expressed in the ganglion cell layer and is co-expressed with NR2E3 in the outer nuclear layer, within rods and cones. Several genes co-targeted by NR2E3 and NR1D1 were identified that include: Nr2c1, Recoverin, Rgr, Rarres2, Pde8a, and Nupr1. We examined the cyclic expression of Nr1d1 and Nr2e3 over a twenty-four hour period and observed that both nuclear receptors cycle in a similar manner. Taken together, these studies reveal a novel role for Nr1d1, in conjunction with its cofactor Nr2e3, in regulating transcriptional networks critical for photoreceptor development and function.

The problem of the competitiveness of nuclear energy: a biophysical explanation

In this study I try to explain the systemic problem of the low economic competitiveness of nuclear energy for the production of electricity by carrying out a biophysical analysis of its production process. Given the fact that neither econometric approaches nor onedimensional methods of energy analyses are effective, I introduce the concept of biophysical explanation as a quantitative analysis capable of handling the inherent ambiguity associated with the concept of energy. In particular, the quantities of energy, considered as relevant for the assessment, can only be measured and aggregated after having agreed on a pre-analytical definition of a grammar characterizing a given set of finite transformations. Using this grammar it becomes possible to provide a biophysical explanation for the low economic competitiveness of nuclear energy in the production of electricity. When comparing the various unit operations of the process of production of electricity with nuclear energy to the analogous unit operations of the process of production of fossil energy, we see that the various phases of the process are the same. The only difference is related to characteristics of the process associated with the generation of heat which are completely different in the two systems. Since the cost of production of fossil energy provides the base line of economic competitiveness of electricity, the (lack of) economic competitiveness of the production of electricity from nuclear energy can be studied, by comparing the biophysical costs associated with the different unit operations taking place in nuclear and fossil power plants when generating process heat or net electricity. In particular, the analysis focuses on fossil-fuel requirements and labor requirements for those phases that both nuclear plants and fossil energy plants have in common: (i) mining; (ii) refining/enriching; (iii) generating heat/electricity; (iv) handling the pollution/radioactive wastes. By adopting this approach, it becomes possible to explain the systemic low economic competitiveness of nuclear energy in the production of electricity, because of: (i) its dependence on oil, limiting its possible role as a carbon-free alternative; (ii) the choices made in relation to its fuel cycle, especially whether it includes reprocessing operations or not; (iii) the unavoidable uncertainty in the definition of the characteristics of its process; (iv) its large inertia (lack of flexibility) due to issues of time scale; and (v) its low power level.

Intercomparison of the response of different photon and neutron detectors around a spent fuel cask

An intercomparison of the response of different photon and neutron detectors was performed in several measurement positions around a spent fuel cask (type TN 12/2B) filled with 4 MOX and 8 UO2 15 x 15 PWR fuel assemblies at the nuclear power plant Gosgen (KKG) in Switzerland. The instruments used in the study were both active and passive, photon and neutron detectors calibrated either for ambient or personal dose equivalent. The aim of the measurement campaign was to compare the responses of the radiation instruments to routinely used detectors. It has been shown that especially the indications of the neutron detectors are strongly dependent on the neutron spectra around the cask due to their different energy responses. However, routinely used active photon and neutron detectors were shown to be reliable instruments. (C) 2012 Elsevier Ltd. All rights reserved.

The Effect of Load Follow Operation on Fuel Behaviour in Loviisa NPP

Työn tarkoituksena oli analysoida polttoainesauvojen käyttäytymistä Loviisan ydinvoimalaitoksen tehonsäätöajossa. Sähkömarkkinoiden vapautuminen Pohjoismaissa sekä tämän seurauksena vaihteleva sähkön markkinahinta ovat ajaneet sähkötuottajat tilanteeseen, jossa tuotanto aiempaa enemmän mukautuu markkinatilanteeseen. Näin ollen myös Loviisan ydinvoimalaitoksen osallistuminen sähkön tuotannon säätelyyn saattaa tulevaisuudessa olla ajankohtaista. Ennen kuin reaktorin tehonsäätöajoa voidaan alkaa toteuttaa, tulee varmistua siitä, että polttoainesauvassa tehonsäätöjen seurauksena tapahtuvat muutokset eivät aiheuta epäsuotuisia käyttäytymisilmiöitä. Työssä tarkastellaan kahden Loviisan ydinvoimalaitoksen polttoainetoimittajan, British Nuclear Fuels plc:n ja venäläisen TVEL:n ensinippujen polttoainesauvan käyttäytymistä tehonsäätötapauksissa. Työssä tarkastellut tehonsäätötapaukset on pyritty valitsemaan niin, että ne kuvaisivat tulevaisuudessa mahdollisesti toteutettavia tehonsäätöjä. Laskentatapauksien sauvatehohistoriat on generoitu HEXBU-3D sydänsimulaattoriohjelmalla lasketun nelivuotisen perustehohistorian pohjalta lisäämällä säätösauvan aiheuttama reaktoritehon muutos, säätösauvan viereisen polttoainenipun aksiaalitehon muutos sekä säätösauvan rakenteen aiheuttama paikallinen tehopiikki säätösauvan vieressä. Työssä tarkastellaan tehonsäätöjen toteuttamista eri tehotasoille ja vaihtelevilla määrillä tehonsäätösyklejä. Työssä käsitellyt laskentatapaukset on jaoteltu reaktorin ajotavan mukaan seuraavasti: peruskuorma-ajo, viikonloppusäätö ja päiväsäätö. Laskenta suoritettiin ydinpolttoaineen käyttäytymistä kuvaavaa ENIGMA-B 7.3.0 ohjelmaa apuna käyttäen. Laskelmien tulokset osoittavat, että molempien polttoainetoimittajien ensinippujen sauvat kestävät reaktorin tehonsäätöajoa rajoituksetta tarkastelluissa laskentatapauksissa. ENIGMA-ohjelman sisältämät mallit, jotka ennustavat polttoainesauvan suojakuoren vaurioitumistodennäköisyyden jännityskorroosion tai väsymismurtuman kautta, eivät näytä mitään merkkejä vaurioitumisesta. BNFL:n polttoainesauva saavuttaa kuitenkin suurempia väsymismurtumatodennäköisyyden arvoja. Tämä johtuu siitä, että polttoainepelletin ja suojakuoren välinen mekaaninen vuorovaikutus syntyy BNFL:n sauvassa aikaisemmin, joka taas johtaa suurempaan määrään sauvaa rasittavia muodonmuutoksia tehonnostotilanteissa. TVEL:n Zr1%Nb -materiaalista valmistetun suojakuoren käyttäytymistä ei voida kuitenkaan suoraan näiden laskujen perusteella arvioida, sillä ENIGMA-ohjelman mallit perustuvat Zircaloy-suojakuorimateriaaleilla suoritettuihin kokeisiin.

Model for subchannel friction factors and flow redistribution in wire-wrapped rod bundles

The fuel element of LMFBR consists of a bundle of rods wrapped with an helical wire as spacer, surrounded by an hexagonal duct. In the present work, a semi-empirical model is developed to calculate bundle average and subchannel based friction factors and flow redistribution. The obtained results were compared to experimental data and they were considered satisfactory for wide range of geometrical parameters.

Experimental analysis of pressure drop and flow redistribution in axial flows in rod bundles

Fuel elements of PWR type nuclear reactors consist of rod bundles, arranged in a square array, and held by spacer grids. The coolant flows, mainly, axially along the rods. Although such elements are laterally open, experiments are performed in closed type test sections, originating the appearance of subchannels with different geometries. In the present work, utilizing a test section of two bundles of 4x4 pins each, experiments were performed to determine the friction and the grid drag coefficients for the different subchannels and to observe the effect of the grids in the crossflow, in cases of inlet flow maldistribution.

Two-phase flow measurements with spacer grid in a rod bundle geometry

Heat transfer effectiveness in nuclear rod bundles is of great importance to nuclear reactor safety and economics. An important design parameter is the Critical Heat Flux (CHF), which limits the transferred heat from the fuel to the coolant. The CHF is determined by flow behaviour, especially the turbulence created inside the fuel rod bundle. Adiabatic experiments can be used to characterize the flow behaviour separately from the heat transfer phenomena in diabatic flow. To enhance the turbulence, mixing vanes are attached to spacer grids, which hold the rods in place. The vanes either make the flow swirl around a single sub-channel or induce cross-mixing between adjacent sub-channels. In adiabatic two-phase conditions an important phenomenon that can be investigated is the effect of the spacer on canceling the lift force, which collects the small bubbles to the rod surfaces leading to decreased CHF in diabatic conditions and thus limits the reactor power. Computational Fluid Dynamics (CFD) can be used to simulate the flow numerically and to test how different spacer configurations affect the flow. Experimental data is needed to validate and verify the used CFD models. Especially the modeling of turbulence is challenging even for single-phase flow inside the complex sub-channel geometry. In two-phase flow other factors such as bubble dynamics further complicate the modeling. To investigate the spacer grid effect on two-phase flow, and to provide further experimental data for CFD validation, a series of experiments was run on an adiabatic sub-channel flow loop using a duct-type spacer grid with different configurations. Utilizing the wire-mesh sensor technology, the facility gives high resolution experimental data in both time and space. The experimental results indicate that the duct-type spacer grid is less effective in canceling the lift force effect than the egg-crate type spacer tested earlier.

Nuclear Magnetic Resonance Study of Hydrated Bentonite

Impedance spectroscopy and nuclear magnetic resonance (NMR) were used to investigate the mobility of water molecules located in the interlayer space of H(+) - exchanged bentonite clay. The conductivity obtained by ac measurements was 1.25 x 10(-4) S/cm at 298 K. Proton ((1)H) lineshapes and spin-lattice relaxation times were measured as a function of temperature over the temperature range 130-320 K. The NMR experiments exhibit the qualitative features associated with the proton motion, namely the presence of a (1)H NMR line narrowing and a well-defined spin-lattice relaxation rate maximum. The temperature dependence of the proton spin-lattice relaxation rates was analyzed with the spectral density function appropriate for proton dynamics in a two-dimensional system. The self-diffusion coefficient estimated from our NMR data, D similar to 2 x 10(-7) cm(2)/s at 300 K, is consistent with those reported for exchanged montmorillonite clay hydrates studied by NMR and quasi-elastic neutron scattering (QNS).

Preconcentration and determination of metal ions from fuel ethanol with a new 2,2'-dipyridylamine bonded silica

A silica surface chemically modified with [3-(2,2'-dipyridylamine) propyl] groups was prepared, characterized, and evaluated for its metal ion preconcentration in fuel ethanol. To our knowledge, we are the first authors who have reported the present modification on silica gel surface. The material was characterized using infrared spectra, scanning electronic microscopy, and 13C and 29Si solid-state NMR spectra. Batch and column experiments were conducted to investigate for metal ion removal from fuel ethanol. The results showed that the Langmuir model describes the sorption equilibrium data of the metal ions in a satisfactory way. From the Langmuir isotherms, the following maximum adsorption capacities (in mmolg -1) were determined: 1.81 for Fe(III), 1.75 for Cr(III), 1.30 for Cu(II), 1.25 for Co(II), 1.15 for Pb(II), 0.95 for Ni(II), and 0.87 for Zn(II). Thermodynamic functions, the change of free energy (ΔG), enthalpy (ΔH), and entropy (ΔS) showed that the adsorption of metal ions onto Si-Pr-DPA was feasible, spontaneous, and endothermic. The sorption-desorption of the metal ions made possible the development of a preconcentration and quantification method of metal ions in fuel ethanol. © 2012 Elsevier Inc.