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.

How to operate a university institute as a radiological emergency service?

The Institute of Radiation Physics (IRA) is attached to the Department of Medical Radiology at the Vaud University Hospital Center (CHUV) in Lausanne. The Institute's main tasks are strongly linked to the medical activities of the Department: radiotherapy, radiodiagnostics, interventional radiology and nuclear medicine. The Institute also works in the fields of operational radiation protection, radiation metrology and radioecology. In the case of an accident involving radioactive materials, the emergency services are able to call on the assistance of radiation protection specialists. In order to avoid having to create and maintain a specific structure, both burdensome and rarely needed, Switzerland decided to unite all existing emergency services for such events. Thus, the IRA was invited to participate in this network. The challenge is therefore to integrate a university structure, used to academic collaborations and the scientific approach, to an interventional organization accustomed to strict policies, a military-style command structure and "drilled" procedures. The IRA's solution entails mobilizing existing resources and the expertise developed through professional experience. The main asset of this solution is that it involves the participation of committed collaborators who remain in a familiar environment, and are able to use proven materials and mastered procedures, even if the atmosphere of an accident situation differs greatly from regular laboratory routines. However, this solution requires both a commitment to education and training in emergency situations, and a commitment in terms of discipline by each collaborator in order to be integrated into a response plan supervised by an operational command center.

Some constraints on the modelling using the uranium isotopes 238U and 234U for dating groundwaters from Guarany aquifer, South America

Groundwaters from the Guarany aquifer located at the South American continent and sampled at four wells with described geological sections in São Paulo State, Brazil, were chemically and isotopically analysed with two aims: to evaluate the quality of this important hydrological resource and to investigate the possibility of using the natural uranium isotopes 234U and 238U as a chronological tool, since the 234U/238U activity ratio and dissolved U content data in groundwater systems have generated models for dating purposes.

Severe Accident Simulation of Small Modular Reactors

Since the Three Mile Island Unit 2 (TMI-2), accident in 1979 which led to the meltdown of about one half of the reactor core and to limited releases of radioactive materials to the environment, an important international effort has been made on severe accident research. The present work aims to investigate the behaviour of a Small Modular Reactor during severe accident conditions. In order to perform these analyses, a SMR has been studied for the European reference severe accident analysis code ASTEC, developed by IRSN and GRS. In the thesis will be described in detail the IRIS Small Modular Reactor; the reference reactor chosen to develop the ASTEC input deck. The IRIS model was developed in the framework of a research collaboration with the IRSN development team. In the thesis will be described systematically the creation of the ASTEC IRIS input deck: the nodalization scheme adopted, the solution used to simulate the passive safety systems and the strong interaction between the reactor vessel and the containment. The ASTEC SMR model will be tested against the RELAP-GOTHIC coupled code model, with respect to a Design Basis Accident, to evaluate the capability of the ASTEC code on reproducing correctly the behaviour of the nuclear system. Once the model has been validated, a severe accident scenario will be simulated and the obtained results along with the nuclear system response will be analysed.

Radiactividad natural de los materiales de construcción. Aplicación al hormigón. Parte I. Radiación externa: índice de riesgo radiactivo

El presente artículo analiza aspectos relacionados con el concepto de radiactividad natural, profundizando en los tipos de radiactividad existente en los materiales naturales radiactivos NORM (“Naturally Occurring Radioactive Materials”) utilizados en la construcción, así como sus fuentes e infl uencias. Este es un artículo que se presenta como la primera parte de un trabajo sobre la radiactividad natural de los materiales de construcción, cuya segunda parte hace referencia a la radiación interna debida al gas radón emitido de manera natural por dichos materiales y se publica por los mismos autores, en esta misma revista. Se aborda la necesidad de establecer criterios de control en este tipo de materiales y se analiza el establecimiento de diferentes índices de riesgo según los distintos países. Al mismo tiempo, se realiza un recorrido por el marco normativo, tanto internacional como nacional, relativo a estos materiales NORM. El presente trabajo es parte de la tesis doctoral de la primera autora del mismo, Beatriz Piedecausa García, a quien el resto de autores agradece su esfuerzo para preparar el texto que ahora se publica y la autorización y las facilidades ofrecidas para acceder a su trabajo.

A pilot study of nuclear medicine reporting through the Medically Oriented Data System /

Mode of access: Internet.

Workshop manual for quality control of scintillation cameras in nuclear medicine /

Mode of access: Internet.

Radiological emergency response : information for the public and the media.

Eleven commercial nuclear reactors used to generate electricity are currently operating at six sites in Illinois; no other state has as many nuclear reactors. In addition, there are two major research facilities in Illinois operated by the US Department of Energy (Argonne National Laboratory and FermiLab), uranium processing facilities at Metropolis and in nearby Paducah, Kentucky, several manufacturers of radiopharmaceuticals and other radioactive materials, thousands of radiation-producing machines used in medicine and industry, and a network of major arterial highways and rail lines over which radioactive material shipments move on a regular basis. Protecting the health and safety of Illinois citizens and the environment from the potentially harmful effects of ionizing radiation is a key function of IEMA'S Division of Nuclear Safety (DNS). That role is fulfilled through programs that monitor nuclear facilities around the clock, ensure the proper operation of radiation-producing equipment and the use of radioactive materials, and measure radioactivity in the environment to ensure no threats to public health exist.

Measures: Monastery for an Atomic Priesthood; Hanford, WA

Thesis (Master's)--University of Washington, 2016-06

The Role of Diffusion in ISOL Targets for the Production of Radioactive Ion Beams

On line isotope separation techniques (ISOL) for production of ion beams of short-lived radionuclides require fast separation of nuclear reaction products from irradiated target materials followed by a transfer into an ion source. As a first step in this transport chain the release of nuclear reaction products from refractory metals has been studied systematically and will be reviewed. High-energy protons (500 - 1000 MeV) produce a large number of radionuclides in irradiated materials via the nuclear reactions spallation, fission and fragmentation. Foils and powders of Re, W, Ta, Hf, Mo, Nb, Zr, Y, Ti and C were irradiated with protons (600 - 1000 MeV) at the Dubna synchrocyclotron, the CERN synchrocyclotron and at the CERN PS-booster to produce different nuclear reaction products. The main topic of the paper is the determination of diffusion coefficients of the nuclear reaction products in the target matrix, data evaluation and a systematic interpretation of the data. The influence of the ionic radius of the diffusing species and the lattice type of the host material used as matrix or target on the diffusion will be evaluated from these systematics. Special attention was directed to the release of group I, II and III-elements. Arrhenius plots lead to activation energies of the diffusion process.