Analysis of a Spanish energy scenario with Generation IV nuclear reactors

The advantages of fast-spectrum reactors consist not only of an efficient use of fuel through the breeding of fissile material and the use of natural or depleted uranium, but also of the potential reduction of the amount of actinides such as americium and neptunium contained in the irradiated fuel. The first aspect means a guaranteed future nuclear fuel supply. The second fact is key for high-level radioactive waste management, because these elements are the main responsible for the radioactivity of the irradiated fuel in the long term. The present study aims to analyze the hypothetical deployment of a Gen-IV Sodium Fast Reactor (SFR) fleet in Spain. A nuclear fleet of fast reactors would enable a fuel cycle strategy different than the open cycle, currently adopted by most of the countries with nuclear power. A transition from the current Gen-II to Gen-IV fleet is envisaged through an intermediate deployment of Gen-III reactors. Fuel reprocessing from the Gen-II and Gen-III Light Water Reactors (LWR) has been considered. In the so-called advanced fuel cycle, the reprocessed fuel used to produce energy will breed new fissile fuel and transmute minor actinides at the same time. A reference case scenario has been postulated and further sensitivity studies have been performed to analyze the impact of the different parameters on the required reactor fleet. The potential capability of Spain to supply the required fleet for the reference scenario using national resources has been verified. Finally, some consequences on irradiated final fuel inventory are assessed. Calculations are performed with the Monte Carlo transport-coupled depletion code SERPENT together with post-processing tools.

Desmantelamiento del experimento EB

Este proyecto consiste en la fase de desmantelamiento de un experimento que se ha ido desarrollando por la empresa AITEMIN en colaboración con multitud de empresas internacionales del ámbito de la eliminación de residuos radioactivos de alta actividad y se desarrolla en el laboratorio subterráneo de Mont Terri en Suiza. En el proyecto se describirán todas las partes del experimento y se procederá a establecer el procedimiento a utilizar para su desmantelamiento, explicando exhaustivamente los pasos a realizar por las personas responsables de la desmantelamiento. ABSTRACT This project involves the dismantling phase of an experiment that has been developed by the company AITEMIN in collaboration with many international companies in the field of radioactive waste disposal and develops high activity in the Mont Terri underground laboratory in Switzerland. The project will describe all parts of the experiment and proceed to establish the procedure to be used for dismantling, thoroughly explaining the steps to be performed by the persons responsible for the dismantling

Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking

The new reactor concepts proposed in the Generation IV International Forum (GIF) are conceived to improve the use of natural resources, reduce the amount of high-level radioactive waste and excel in their reliability and safe operation. Among these novel designs sodium fast reactors (SFRs) stand out due to their technological feasibility as demonstrated in several countries during the last decades. As part of the contribution of EURATOM to GIF the CP-ESFR is a collaborative project with the objective, among others, to perform extensive analysis on safety issues involving renewed SFR demonstrator designs. The verification of computational tools able to simulate the plant behaviour under postulated accidental conditions by code-to-code comparison was identified as a key point to ensure reactor safety. In this line, several organizations employed coupled neutronic and thermal-hydraulic system codes able to simulate complex and specific phenomena involving multi-physics studies adapted to this particular fast reactor technology. In the “Introduction” of this paper the framework of this study is discussed, the second section describes the envisaged plant design and the commonly agreed upon modelling guidelines. The third section presents a comparative analysis of the calculations performed by each organisation applying their models and codes to a common agreed transient with the objective to harmonize the models as well as validating the implementation of all relevant physical phenomena in the different system codes.

Hearing on H.R. 2504 [microform] : to withdraw certain public lands in Eddy County, New Mexico : before the Procurement and Military Nuclear Systems Subcommittee of the Committee on Armed Services, House of Representatives, One Hundredth Congress, second session, hearing held September 8, 1988.

At head of title: H.A.S.C. no. 100-85.

The ... baseline environmental management report.

Title from cover.

Retention efficiencies of charcoal traps for fission gases : technical report /

"August 23, 1957."

Retention efficiencies of selected adsorbents for krypton : technical report /

"April 15, 1958."

Gasket failures in plutonium reduction furnaces MT-27-64 /

"RFP-435 ; UC-38 Engineering and Equipment ; TID-4500 (34th Ed.)."

Hydrologic and tracer studies in Mohawk River at Knolls Atomic Power Laboratory /

"Unclassified."

United States' sea disposal operations : a summary to December 1956 /

"WASH-734."

Behavior of certain radionuclides released into fresh-water environments; annual report.

Public Health Service publication no. 999-RH.

Baseline environmental management report.

The Baseline Environmental Management Report (Baseline Report) is an analytical tool to help guide the Departmental decisions and provide an accounting of the Department's progress, spending, and plans. In addition to illustrating the assumed path forward, the 1996 Baseline Report presents policy analyses that examine the consequences of modifying key program assumptions.

West Valley cooperative agreement [microform] : hearing before the Subcommittee on Investigations and Oversight of the Committee on Science and Technology, U.S. House of Representatives, Ninety-seventh Congress, first session, July 9, 1981.

"No. 26."

Site characterization progress report, Yucca Mountain, Nevada : April 1, 1990-September 30, 1990.

"March 1991."

Physical properties data for rock salt /

Mode of access: Internet.