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Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants; Perspectives a long terme des couts de traitement de l'uranium naturel irradie. Tailles et localisations optimales des usines

Abstract

The aim of this paper is to help solve the problem of the selection of optimal sizes and sites for spent nuclear fuel processing plants associated with power capacity programmes already installed. Firstly, the structure of capital and running costs of irradiated natural uranium processing plants is studied, as well as the influence of plant sizes on these costs and structures. Shipping costs from the production site to the plant must also be added to processing costs. An attempt to reach a minimum cost for the production of a country or a group of countries must therefore take into account both the size and the location of the plants. The foreseeable shipping costs and their structure (freight, insurance, container cost and depreciation), for spent natural uranium are indicated. Secondly, for various annual spent fuel reprocessing programmes, the optimal sizes and locations of the plants are determined. The sensitivity of the results to the basic assumptions relative to processing costs, shipping costs, the starting up year of the plant programme and the length of period considered, is also tested. - this rather complex problem, of a combinative nature, is solved through dynamic programming methods. - It is shown that these methods  More>>
Authors:
Thiriet, L; [1]  Oger, C; Vaumas, P de [2] 
  1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires
  2. Saint-Gobain Nucleaire, 92 - Courbevoie (France)
Publication Date:
Jul 01, 1964
Product Type:
Technical Report
Report Number:
CEA-R-2642
Resource Relation:
Other Information: 3 refs
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; COST ESTIMATION; ECONOMIC ANALYSIS; FUEL REPROCESSING PLANTS; LIFE-CYCLE COST; MANAGEMENT; NATURAL URANIUM; REPROCESSING; SPENT FUELS
OSTI ID:
20668336
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
English; French
Other Identifying Numbers:
TRN: FR05R2642107037
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
33 pages
Announcement Date:
Dec 19, 2005

Citation Formats

Thiriet, L, Oger, C, and Vaumas, P de. Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants; Perspectives a long terme des couts de traitement de l'uranium naturel irradie. Tailles et localisations optimales des usines. France: N. p., 1964. Web.
Thiriet, L, Oger, C, & Vaumas, P de. Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants; Perspectives a long terme des couts de traitement de l'uranium naturel irradie. Tailles et localisations optimales des usines. France.
Thiriet, L, Oger, C, and Vaumas, P de. 1964. "Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants; Perspectives a long terme des couts de traitement de l'uranium naturel irradie. Tailles et localisations optimales des usines." France.
@misc{etde_20668336,
title = {Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants; Perspectives a long terme des couts de traitement de l'uranium naturel irradie. Tailles et localisations optimales des usines}
author = {Thiriet, L, Oger, C, and Vaumas, P de}
abstractNote = {The aim of this paper is to help solve the problem of the selection of optimal sizes and sites for spent nuclear fuel processing plants associated with power capacity programmes already installed. Firstly, the structure of capital and running costs of irradiated natural uranium processing plants is studied, as well as the influence of plant sizes on these costs and structures. Shipping costs from the production site to the plant must also be added to processing costs. An attempt to reach a minimum cost for the production of a country or a group of countries must therefore take into account both the size and the location of the plants. The foreseeable shipping costs and their structure (freight, insurance, container cost and depreciation), for spent natural uranium are indicated. Secondly, for various annual spent fuel reprocessing programmes, the optimal sizes and locations of the plants are determined. The sensitivity of the results to the basic assumptions relative to processing costs, shipping costs, the starting up year of the plant programme and the length of period considered, is also tested. - this rather complex problem, of a combinative nature, is solved through dynamic programming methods. - It is shown that these methods can also be applied to the problem of selecting the optimal sizes and locations of processing plants for MTR type fuel elements, related to research reactor programmes, as well as to future plutonium element processing plants related to breeder reactors. Thirdly, the case where yearly extraction of the plutonium contained in the irradiated natural uranium is not compulsory is examined; some stockpiling of the fuel is then allowed some years, entailing delayed processing. The load factor of such plants is thus greatly improved with respect to that of plants where the annual plutonium demand is strictly satisfied. By including spent natural uranium stockpiling costs an optimal rhythm of introduction and optimal sizes for spent fuel processing plants are shown, different from those in part two. The indirect effect of these reprocessing programmes on the availability of plutonium, and therefore on the possibility.of undertaking plutonium burning reactor programmes, must be taken into account. (authors) [French] L'objet de cette communication est d'apporter une contribution a la solution du probleme du choix des tailles et des localisations optimales des usines de traitement des combustibles nucleaires irradies, associees a des programmes de puissance electrique installee. Dans une premiere partie, on etudie la structure des couts d'investissements et d'exploitation des usines de traitement de l'uranium naturel irradie, l'influence de la taille des usines sur ces couts et ces structures de couts. Au cout de traitement de l'uranium naturel irradie s'ajoute d'autre part le cout du transport des combustibles irradies des lieux de production aux sites des usines de traitement. La recherche du cout minimum pour la production d'un pays ou d'un ensemble de pays fait donc intervenir a la fois la taille et la localisation des usines. On indique les couts de transport previsibles pour l'uranium naturel irradie et la structure de ces couts (transport, assurance, couts et amortissement des containers). Dans une deuxieme partie, et pour differents echeanciers de combustibles irradies a traiter chaque annee, on determine les tailles et les localisations optimales des usines de traitement et la sensibilite de ces resultats, aux hypotheses de base concernant le cout du traitement, le cout du transport, l'annee de demarrage du programme d'usines, l'horizon choisi. - le probleme de nature combinatoire, assez complexe, est resolu par l'application des methodes de la programmation dynamique. - on montre que les methodes sont egalement applicables au probleme du choix des tailles et des localisations optimales des usines de traitement des elements du type MTR, associees aux programmes de reacteurs de recherche ainsi qu'aux futures usines de traitement des elements au plutonium associees aux reacteurs surregenerateurs. Dans une troisieme partie, on etudie le cas ou l'on ne s'impose pas d'extraire chaque annee le plutonium contenu dans l'uranium naturel irradie, et ou on peut admettre un certain stockage du combustible certaines annees, conduisant a un traitement differe. Le facteur de charge de telles usines est alors tres ameliore par rapport a celui des usines ou la demande en plutonium est chaque annee satisfaite strictement. On montre en introduisant les couts de stockage de l'uranium naturel irradie, qu'il existe une cadence et des tailles optimales des usines de traitement des combustibles irradies differentes du cas de la 2eme partie. On doit tenir compte en particulier de l'effet indirect de ces programmes de traitement sur la disponibilite de Pu, donc sur les possibilites de realisation de programmes de reacteurs utilisant ce Pu. (auteurs)}
place = {France}
year = {1964}
month = {Jul}
}