Development of fabrication techniques and manufacturing specifications for APPR fuel plates /

"Contract No. AT(30-1)GEN-366 Sposored Task C-50."

Quantitative determination of uranium loading of aluminum-clad fuel plates by x-ray densitometry /

Work performed at the Sylvania-Corning Nuclear Corporation under Contract AT(30-1) GEN-366.

Ceramic fuel elements made by hot isostatic pressing /

Work performed at the Sylvania-Corning Nuclear Corporation under contract AT-30-1 GEN-366 with the Division of Reactor Development.

Reviewing the Nuclear Nonproliferation Treaty (NPT) /

"As currently interpreted, it is difficult to see why the Nuclear Nonproliferation Treaty (NPT) warrants much support as a nonproliferation convention. Most foreign ministries, including that of Iran and the United States, insist that Article IV of the NPT recognizes all states' "inalienable right" of all states to develop "peaceful nuclear energy". This includes money-losing activities, such as nuclear fuel reprocessing, which can bring countries to the very brink of acquiring nuclear weapons. If the NPT is intended to ensure that states share peaceful "benefits" of nuclear energy and to prevent the spread of nuclear bomb making technologies, it is difficult to see how it can accomplish either if the interpretation identified above is correct."--P. 3

Commercial nuclear power.

"DOE/EIA-0438."

A new age of fuel performance code criteria studied through advanced atomistic simulation techniques

A fundamental step in understanding the effects of irradiation on metallic uranium and uranium dioxide ceramic fuels, or any material, must start with the nature of radiation damage on the atomic level. The atomic damage displacement results in a multitude of defects that influence the fuel performance. Nuclear reactions are coupled, in that changing one variable will alter others through feedback. In the field of fuel performance modeling, these difficulties are addressed through the use of empirical models rather than models based on first principles. Empirical models can be used as a predictive code through the careful manipulation of input variables for the limited circumstances that are closely tied to the data used to create the model. While empirical models are efficient and give acceptable results, these results are only applicable within the range of the existing data. This narrow window prevents modeling changes in operating conditions that would invalidate the model as the new operating conditions would not be within the calibration data set. This work is part of a larger effort to correct for this modeling deficiency. Uranium dioxide and metallic uranium fuels are analyzed through a kinetic Monte Carlo code (kMC) as part of an overall effort to generate a stochastic and predictive fuel code. The kMC investigations include sensitivity analysis of point defect concentrations, thermal gradients implemented through a temperature variation mesh-grid, and migration energy values. In this work, fission damage is primarily represented through defects on the oxygen anion sublattice. Results were also compared between the various models. Past studies of kMC point defect migration have not adequately addressed non-standard migration events such as clustering and dissociation of vacancies. As such, the General Utility Lattice Program (GULP) code was utilized to generate new migration energies so that additional non-migration events could be included into kMC code in the future for more comprehensive studies. Defect energies were calculated to generate barrier heights for single vacancy migration, clustering and dissociation of two vacancies, and vacancy migration while under the influence of both an additional oxygen and uranium vacancy.

Desenvolvimento e validação de metodologia analítica para quantificação de urânio em compostos do ciclo do combustível nuclear por espectroscopia no infravermelho com transformada de Fourier (FTIR)

Tese (Doutorado em Tecnologia Nuclear)

Sähkön tuotantokustannusvertailu

Työssä vertaillaan eri sähköntuotantovaihtoehtojen taloudellista kannattavuutta. Kannattavuusvertailu suoritetaan pelkkää sähköä tuottaville voimalaitoksille. Sähkön ja lämmön yhteistuotannon lisärakentaminen tulee kattamaan tietyn osuuden lähitulevaisuuden sähkön hankinnan vajeesta, mutta sen lisäksi tarvitaan myös uutta lauhdetuotantokapasiteettia. Tutkittavat voimalaitostyypit ovat: ydinvoimalaitos, maakaasukombilauhdevoimalaitos, kivihiililauhdevoimalaitos, turvelauhdevoimalaitos, puulauhdevoimalaitos ja tuulivoimala. Kannattavuustarkastelu suoritetaan annuiteettimenetelmällä käyttäen 5 % reaalikorkoa ja tammikuun 2008 hintatasoa. Laskelmien perusteella 8000 tunnin huipunkäyttöajalla ydinsähkön tuotantokustannus olisi 35,0 € /MWh, kaasusähkön 59,2 €/MWh ja hiilisähkön 64,4 €/MWh, kun hiilidioksidipäästöoikeuden hintana käytetään 23 €/t. Ilman päästökauppaa kaasusähkön hinta on 51,2 €/MWh ja hiilisähkön 45,7 €/MWh ydinsähkön hinnan pysyessä ennallaan. Herkkyystarkastelun tulosten perusteella ydinvoiman kilpailukyky korostuu muihin tarkasteltuihin tuotantomuotoihin verrattuna. Ydinpolttoaineen suurellakaan hinnan muutoksella ei ole merkittävää vaikutusta ydinsähkön tuotantokustannukseen, kun taas maakaasusähkö on erittäin riippuvainen polttoaineen hinnasta. Myös päästöoikeuden hinnan kasvu lisää merkittävästi ydinvoiman kilpailukykyä kaasu- ja hiilisähköön verrattuna. Ydinvoimainvestoinnin kannattavuutta ja takaisinmaksua tarkastellaan myös yksinään siten, että investoinnilla saavutettavien tuottojen laskennassa käytetään useita eri sähkön markkinahintoja. Investoinnin kannattavuus on erittäin hyvä, kun sähkön markkinahinta on 50 €/MWh tai suurempi.

Comparison of electricity generation costs

The economical competitiveness of various power plant alternatives is compared. The comparison comprises merely electricity producing power plants. Combined heat and power (CHP) producing power will cover part of the future power deficit in Finland, but also condensing power plants for base load production will be needed. The following types of power plants are studied: nuclear power plant, combined cycle gas turbine plant, coal-fired condensing power plant, peat-fired condensing power plant, wood-fired condensing power plant and wind power plant. The calculations are carried out by using the annuity method with a real interest rate of 5 % per annum and with a fixed price level as of January 2008. With the annual peak load utilization time of 8000 hours (corresponding to a load factor of 91,3 %) the production costs would be for nuclear electricity 35,0 €/MWh, for gas based electricity 59,2 €/MWh and for coal based electricity 64,4 €/MWh, when using a price of 23 €/tonCO2 for the carbon dioxide emission trading. Without emission trading the production cost of gas electricity is 51,2 €/MWh and that of coal electricity 45,7 €/MWh and nuclear remains the same (35,0 €/MWh) In order to study the impact of changes in the input data, a sensitivity analysis has been carried out. It reveals that the advantage of the nuclear power is quite clear. E.g. the nuclear electricity is rather insensitive to the changes of nuclear fuel price, whereas for natural gas alternative the rising trend of gas price causes the greatest risk. Furthermore, increase of emission trading price improves the competitiveness of the nuclear alternative. The competitiveness and payback of the nuclear power investment is studied also as such by using various electricity market prices for determining the revenues generated by the investment. The profitability of the investment is excellent, if the market price of electricity is 50 €/MWh or more.

Suomen ydinpolttoainekierto

Suomessa on nykyisin käytössä avoimen ydinpolttoainekierron politiikka missä käytetty polttoaine loppusijoitetaan suoraan ilman jälleenkäsittelyä. Nykyisin kehitteillä olevat uuden sukupolven ydinreaktorit ovat kuitenkin pääosin suunniteltu osittain tai kokonaan suljetuille polttoainekierroille, joissa käytetty polttoaine jälleenkäsitellään ja osa materiaaleista kierrätetään. Tässä tutkimusraportissa on tarkoitus arvioida Suomen ydinvoimakapasiteetin ja ydinpolttoainekierron kehitystä tulevina vuosikymmeninä sekä arvioida käytetyn polttoaineen jälleenkäsittelyn, kierrätyksen ja nopeiden reaktoreiden käyttöönoton vaikutusta muun muassa uraanin kulutukseen, syntyvän käytetyn polttoaineen määrään sekä polttoainekierron taloudellisuuteen. Lisäksi työssä arvioidaan Talvivaaran ja Soklin sivutuotteena saatavan uraanin riittävyyttä Suomen uraanintarpeen kattamiseksi. Työssä arvioitiin ensin oletuksien ja nykyisen tilanteen avulla Suomen ydinvoimakapasiteetin kehitys tuleville vuosille. Perustuen tähän kehitykseen nykyistä polttoainekiertoa verrattiin tämän jälkeen kahteen kehittyneempään polttoainekiertoversioon, joissa käytetty polttoaine jälleenkäsitellään, plutonium kierrätetään uudelleen polttoaineeksi ja osa termisistä reaktoreista korvataan nopeilla. Polttoainekiertoversioiden massavirtojen määrittämisessä käytettiin apuna kansainvälisen atomienergiajärjestön kehittämää Nuclear Fuel Cycle Simulation System -ohjelmaa. Nykyisellä polttoainekierrolla uraanintarve oli laskelmien perusteella noin 100 tuhatta tonnia vuoteen 2100 mennessä. Jälleenkäsittelyn ja plutoniumin kierrätyksen avulla uraanin tarve saatiin pudotettua noin 75 tuhanteen tonniin. Korvaamalla puolet ydinvoimakapasiteetista nopeilla reaktoreilla vuosina 2074 ja 2080 vähentäisi uraanintarvetta edelleen noin 66 tuhanteen tonniin. Kerääntyneen käytetyn polttoaineen määräksi arvioitiin nykyisen kaltaisella polttoainekierrolla noin 11900 tonnia vuoteen 2100 mennessä. Nopeiden reaktoreiden käyttöönoton myötä kerääntyneen käytetyn polttoaineen määrä vähenisi edelleen noin 11200 tonniin vuoteen 2100 mennessä. Talvivaaran ja Soklin uraanintuotanto riittäisi laskelmien mukaan kattamaan Suomen uraanintarpeen nykyisellä polttoainekierrolla vuoteen 2070 asti ja kehittyneemmillä polttoainekierroilla vuosiin 2089 ja 2106 asti riippuen polttoainekierrosta. Polttoainekierron kustannukset nousivat polttoaineen jälleenkäsittelyn ja kierrätyksen myötä noin 50-67 % suuremmiksi nykyiseen polttoainekiertoon verrattuna. Investointi- sekä käyttö- ja kunnossapitokustannuksien erot olivat eri versioiden välillä pienet, mistä johtuen myös kokonaiskustannuksien erot jäivät pieniksi.

Ydinpolttoaineen lämmönsiirto

Kandidaatintyössä perehdytään ydinpolttoaineessa tapahtuvaan lämmönsiirtoon ja lämmönsiirron ilmiöihin. Lämmönsiirron tarkastelussa keskitytään erityisesti polttoainepelletissä tapahtuvaan lämmönsiirtoon, mutta työn edetessä esitellään myös lyhyesti lämmön siirtyminen polttoainepelletistä kaasunraon ja polttoainesauvan suojakuoren läpi jäähdytteeseen. Kandidaatintyössä tarkastellaan myös kiinteiden ydinpolttoaineiden lämmönsiirto-ominaisuuksia. Lämmönsiirto-ominaisuudet riippuvat materiaalien termodynaamisista ja kemiallisista ominaisuuksista. Lämmönsiirto-ominaisuuksien tunteminen on edellytys uusien, lämmönsiirrollisesti entistä parempien, polttoaineiden kehittämiselle.

Circular Spectropolarimetric Studies of DQ White Dwarfs

This thesis summarizes studies of a class of white dwarfs (WDs) called DQ WDs. White dwarfs are the remnants of ordinary stars like our Sun that have run out of nuclear fuel. WDs are classified according to the composition of their atmosphere and DQ WDs have an atmosphere made of helium and carbon. The carbon comes in either atomic or molecular form and in some cases the strong spectral absorption features cover the entire optical wavelength region. The research presented here utilizes spectropolarimetry, which is an observational technique that combines spectroscopy and polarization. Separately these allow to study the composition of a target and the inhomogeneous distribution of matter in the target. Put together they form a powerful tool to probe the physical properties in the atmosphere of a star. It is espacially good for detecting magnetic fields. The papers in this thesis describe efforts to do a survey of DQ white dwarfs with spectropolarimetry in order to search for magnetic fields in them. Paper I describes the discovery of a new magnetic cool DQ white dwarf, GJ841B. Initial modeling of molecular features on DQ WDs showed inconsistencies with observations. The first possible solution to this problem was stellar spots on these WDs. To investigate the matter, two DQ WDs were monitored for photometric variability that could arise from the presence of such spots. Paper II summarizes this short campaign and reports the negative results. Paper III reports observations of the rest of the objects in our survey. The paper includes the discovery of polarization from another cool DQ white dwarf, bringing the total of known magnetic cool DQs to three. Unfortunately the model used in this thesis cannot, in its present state, be used to model these objects nor are the observations of high enough spectroscopic resolution to do so.

Thermalhydraulic behavior of electrically heated rod during a critical heat flux transient

In nuclear reactors, the occurrence of critical heat flux leads to fuel rod overheating with clad fusion and radioactive products leakage. To predict the effects of such phenomenon, experiments are performed using electrically heated rods to simulate operational and accidental conditions of nuclear fuel rods. In the present work, it is performed a theoretical analysis of the drying and rewetting front propagation during a critical heat flux experiment, starting with the application of an electrical power step from steady state condition. After the occurrence of critical heat flux, the drying front propagation is predicted. After a few seconds, a power cut is considered and the rewetting front behavior is analytically observed. Studies performed with various values of coolant mass flow rate show that this variable has more influence on the drying front velocity than on the rewetting one.

Some new strategies for the chemical separation of actinides and lanthanides

A future goal in nuclear fuel reprocessing is the conversion or transmutation of the long-lived radioisotopes of minor actinides, such as americium, into short-lived isotopes by irradiation with neutrons. In order to achieve this transmutation, it is necessary to separate the minor actinides(III), [An(Ill)], from the lanthanides(III), [Ln(Ill)], by solvent extraction (partitioning), because the lanthanides absorb neutrons too effectively and hence limit neutron capture by the transmutable actinides. Partitioning using ligands containing only carbon, hydrogen, nitrogen and oxygen atoms is desirable because they are completely incinerable and thus the final volume of waste is minimised [1]. Nitric acid media will be used in the extraction experiments because it is envisaged that the An(III)/Ln(III) separation process could take place after the PUREX process. There is no doubt that the correct design of a molecule that is capable of acting as a ligand or extraction reagent is required for the effective separation of metal ions such as actinides(III) from lanthanides. Recent attention has been directed towards heterocyclic ligands with for the preferential separation of the minor actinides. Although such molecules have a rich chemistry, this is only now becoming sufficiently well understood in relation to the partitioning process [2]. The molecules shown in Figures I and 2 will be the principal focus of this study. Although the examples chosen here are used rather specific, the guidelines can be extended to other areas such as the separation of precious metals [3].

Use of soft heterocyclic N‑donor ligands to separate actinides and lanthanides

The removal of the most long-lived radiotoxic elements from used nuclear fuel, minor actinides, is foreseen as an essential step toward increasing the public acceptance of nuclear energy as a key component of a low-carbon energy future. Once removed from the remaining used fuel, these elements can be used as fuel in their own right in fast reactors or converted into shorter-lived or stable elements by transmutation prior to geological disposal. The SANEX process is proposed to carry out this selective separation by solvent extraction. Recent efforts to develop reagents capable of separating the radioactive minor actinides from lanthanides as part of a future strategy for the management and reprocessing of used nuclear fuel are reviewed. The current strategies for the reprocessing of PUREX raffinate are summarized, and some guiding principles for the design of actinide-selective reagents are defined. The development and testing of different classes of solvent extraction reagent are then summarized, covering some of the earliest ligand designs right through to the current reagents of choice, bis(1,2,4-triazine) ligands. Finally, we summarize research aimed at developing a fundamental understanding of the underlying reasons for the excellent extraction capabilities and high actinide/lanthanide selectivities shown by this class of ligands and our recent efforts to immobilize these reagents onto solid phases.