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Quantitative Evaluation of Nuclear Power Station Siting from the Point of View of Safety; Evaluacion Cuantitativa del Emplazamiento de Centrales Nucleoelectricas desde el Punto de Vista de la Seguridad

Abstract

Apart from the minimum operational and safety requirements for the siting of nuclear power stations, the paper proposes introducing the total mean dose to the general population as an additional criterion. Although the calculation of this dose presupposes a detailed knowledge of the main pathways by which the population may be irradiated in case of an accident, the present state of power reactor technology makes it possible to tackle the problem already. An estimate of the total mean dose per unit time involves the safety aspects of the reactor, the features of the site considered, and the way in which these features affect safety. The authors derive the general formula expressing the total mean dose as a function of all the parameters concerned. It is pointed out that in the case of accidents in which the release of fission products is independent of the mechanisms of irradiation, this formula is considerably simplified and makes it possible to establish a classification of the relative suitability, from the safety point of view, of the sites proposed, without touching upon the difficult problem of the definition of accidents and their probabilities of occurrence. A further simplification accrues when there exist predominant mechanisms governing  More>>
Authors:
Serment Cabrero, V.; [1]  Velez, C. [2] 
  1. Comision Nacional de Energia Nuclear y Universidad Nacional Autonomia de Mexico (Mexico)
  2. Instituto Politecnico Nacional y Comision Federal de Electricidad (Mexico)
Publication Date:
Sep 15, 1967
Product Type:
Conference
Report Number:
IAEA-SM-89/57
Resource Relation:
Conference: Symposium on the Containment and Siting of Nuclear Power Plants, Vienna (Austria), 3-7 Apr 1967; Other Information: 10 refs.; Related Information: In: Containment and Siting of Nuclear Power Plants. Proceedings of a Symposium on the Containment and Siting of Nuclear Power Plants| 836 p.
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 54 ENVIRONMENTAL SCIENCES; CLASSIFICATION; DIGITAL COMPUTERS; ENVIRONMENTAL EXPOSURE; FISSION PRODUCT RELEASE; NUCLEAR POWER PLANTS; RADIATION ACCIDENTS; RADIATION DOSES; REACTOR SITES; SAFETY ANALYSIS; SAFETY STANDARDS; SITE SELECTION
OSTI ID:
22121080
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
Spanish
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M1309077173
Submitting Site:
INIS
Size:
page(s) 183-189
Announcement Date:
Aug 16, 2013

Citation Formats

Serment Cabrero, V., and Velez, C. Quantitative Evaluation of Nuclear Power Station Siting from the Point of View of Safety; Evaluacion Cuantitativa del Emplazamiento de Centrales Nucleoelectricas desde el Punto de Vista de la Seguridad. IAEA: N. p., 1967. Web.
Serment Cabrero, V., & Velez, C. Quantitative Evaluation of Nuclear Power Station Siting from the Point of View of Safety; Evaluacion Cuantitativa del Emplazamiento de Centrales Nucleoelectricas desde el Punto de Vista de la Seguridad. IAEA.
Serment Cabrero, V., and Velez, C. 1967. "Quantitative Evaluation of Nuclear Power Station Siting from the Point of View of Safety; Evaluacion Cuantitativa del Emplazamiento de Centrales Nucleoelectricas desde el Punto de Vista de la Seguridad." IAEA.
@misc{etde_22121080,
title = {Quantitative Evaluation of Nuclear Power Station Siting from the Point of View of Safety; Evaluacion Cuantitativa del Emplazamiento de Centrales Nucleoelectricas desde el Punto de Vista de la Seguridad}
author = {Serment Cabrero, V., and Velez, C.}
abstractNote = {Apart from the minimum operational and safety requirements for the siting of nuclear power stations, the paper proposes introducing the total mean dose to the general population as an additional criterion. Although the calculation of this dose presupposes a detailed knowledge of the main pathways by which the population may be irradiated in case of an accident, the present state of power reactor technology makes it possible to tackle the problem already. An estimate of the total mean dose per unit time involves the safety aspects of the reactor, the features of the site considered, and the way in which these features affect safety. The authors derive the general formula expressing the total mean dose as a function of all the parameters concerned. It is pointed out that in the case of accidents in which the release of fission products is independent of the mechanisms of irradiation, this formula is considerably simplified and makes it possible to establish a classification of the relative suitability, from the safety point of view, of the sites proposed, without touching upon the difficult problem of the definition of accidents and their probabilities of occurrence. A further simplification accrues when there exist predominant mechanisms governing the accidental irradiation of the population. The approach adopted is particularly well suited to calculations with digital computers, and helps to identify the areas in which information is lacking and to direct research intended to remove these deficiencies. (author) [Spanish] Ademas de los requisitos mfnimos opecacionales y de seguridad para el emplazamiento de centrales nucleoelectricas, se sugiere utilizar como criterio adicional la dosis total promedio a la poblacion. Aunque el calculo de esa dosis implica el conocimiento detallado de los caminos principales por los cuales la poblacion puede ser irradiada en el caso de un accidente, el estado actual de la tecnologia de los reactores nucleares de potencia permite ya abordar el problema. En la estimacion de la dosis total promedio por unidad de tiempo intervienen los aspectos de seguridad del reactor, las caracteristicas del lugar considerado y la forma como estas afectan dicha seguridad. Se obtiene la formula general que expresa la dosis total promedio en funcion de todos los parametros involucrados. Se hace notar que para la clase de accidentes en que la liberacion de productos de fision es independiente de los mecanismos de irradiacion, dicha formula se simplifica considerablemente y permite obtener una clasificacion de la bondad relativa de los lugares propuestos, desde el punto de vista de la seguridad, sin entrar en el problema dificil de la definicion de accidentes y de las probabilidades de que ocurran. Una simplificacion adicional se obtiene cuando existen mecanismos dominantes en la irradiacion accidental de la poblacion. La formulacion escogida se adapta especialmente al calculo mediante computadoras digitales y permite identificar las areas en que se carece de la informacion necessaria y orientar por tanto la investigacion para remediar esas insuficiencias. (author)}
place = {IAEA}
year = {1967}
month = {Sep}
}