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The Why and How of Nuclear Accident Dosimetry; Dosimetrie en cas d'Accident Nucleaire: Raison d'Etre et Modalites; 041e 0411 041e 0421 041d 041e 0412 0414 ; Dosimetria en Casos de Accidente Nuclear: Justificacion y Modalidades

Conference:

Abstract

The objective of an effective nuclear accident dosimetry programme is to ensure that a means is provided for estimating the gamma neutron dose from a nuclear accident. In this connection, the limitation of the film badge is discussed, in addition to certain accident experiences which demonstrate the need for an effective accident dosimetry programme at facilities having a potential for nuclear accidents. Certain basic parameters should be considered in the development of an effective nuclear accident dosimetry programme. These are (a) a method for screening personnel involved in nuclear accidents, (b) a fixed system (primary unit) capable of determining first collision dose within some established degree of accuracy at its point of location, (c) the need for ''secondary units'', and (d) the need for a device worn by personnel which would afford spectrum and flux information to assist in dose extrapolation from the fixed unit to the location of man. The neutron component of the system should permit flux and spectral information in order to arrive at appropriate quality factors in the dose estimation. Accuracies should be established based upon the current state of the art. The gamma -ray component of the system should permit measuring gamma radiation within the  More>>
Authors:
Vallario, E. J.; Wasson, H. R. [1] 
  1. United States Atomic Energy Commission, Washington, DC (United States)
Publication Date:
Jun 15, 1965
Product Type:
Conference
Report Number:
IAEA-SM-56/9
Resource Relation:
Conference: Symposium on Personnel Dosimetry for Accidental High-Level Exposure to External and Internal Radiation, Vienna (Austria), 8-12 Mar 1965; Other Information: 6 refs., 4 figs., 2 tabs.; Related Information: In: Personnel Dosimetry for Radiation Accidents. Proceedings of a Symposium on Personnel Dosimetry for Accidental High-Level Exposure to External and Internal Radiation| 732 p.
Subject:
61 RADIATION PROTECTION AND DOSIMETRY; ACCURACY; EXTRAPOLATION; FISSION SPECTRA; GAMMA RADIATION; NEUTRONS; PERSONNEL DOSIMETRY; PHOTOGRAPHIC FILM DOSEMETERS; QUALITY FACTOR; RADIATION ACCIDENTS; RADIATION DOSES; REACTOR ACCIDENTS
OSTI ID:
22202913
Research Organizations:
International Atomic Energy Agency, Vienna (Austria); World Health Organization, Geneva (Switzerland)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0074-1884; TRN: XA13M3603023824
Submitting Site:
INIS
Size:
page(s) 31-44
Announcement Date:
Mar 06, 2014

Conference:

Citation Formats

Vallario, E. J., and Wasson, H. R. The Why and How of Nuclear Accident Dosimetry; Dosimetrie en cas d'Accident Nucleaire: Raison d'Etre et Modalites; 041e 0411 041e 0421 041d 041e 0412 0414 ; Dosimetria en Casos de Accidente Nuclear: Justificacion y Modalidades. IAEA: N. p., 1965. Web.
Vallario, E. J., & Wasson, H. R. The Why and How of Nuclear Accident Dosimetry; Dosimetrie en cas d'Accident Nucleaire: Raison d'Etre et Modalites; 041e 0411 041e 0421 041d 041e 0412 0414 ; Dosimetria en Casos de Accidente Nuclear: Justificacion y Modalidades. IAEA.
Vallario, E. J., and Wasson, H. R. 1965. "The Why and How of Nuclear Accident Dosimetry; Dosimetrie en cas d'Accident Nucleaire: Raison d'Etre et Modalites; 041e 0411 041e 0421 041d 041e 0412 0414 ; Dosimetria en Casos de Accidente Nuclear: Justificacion y Modalidades." IAEA.
@misc{etde_22202913,
title = {The Why and How of Nuclear Accident Dosimetry; Dosimetrie en cas d'Accident Nucleaire: Raison d'Etre et Modalites; 041e 0411 041e 0421 041d 041e 0412 0414 ; Dosimetria en Casos de Accidente Nuclear: Justificacion y Modalidades}
author = {Vallario, E. J., and Wasson, H. R.}
abstractNote = {The objective of an effective nuclear accident dosimetry programme is to ensure that a means is provided for estimating the gamma neutron dose from a nuclear accident. In this connection, the limitation of the film badge is discussed, in addition to certain accident experiences which demonstrate the need for an effective accident dosimetry programme at facilities having a potential for nuclear accidents. Certain basic parameters should be considered in the development of an effective nuclear accident dosimetry programme. These are (a) a method for screening personnel involved in nuclear accidents, (b) a fixed system (primary unit) capable of determining first collision dose within some established degree of accuracy at its point of location, (c) the need for ''secondary units'', and (d) the need for a device worn by personnel which would afford spectrum and flux information to assist in dose extrapolation from the fixed unit to the location of man. The neutron component of the system should permit flux and spectral information in order to arrive at appropriate quality factors in the dose estimation. Accuracies should be established based upon the current state of the art. The gamma -ray component of the system should permit measuring gamma radiation within the biological area of interest, i. e. from 10 to 10{sup 3}r. Consideration for the number, placement and ease of recovery of accident units are indeed an integral part of an effective system of accident dosimetry. These considerations should enable reasonable data collection across the entire fission spectrum. (author) [French] L'objet d'un programme efficace de dosimetrie en cas d'accident nucleaire est d'evaluer la dose de rayons gamma et de neutrons emise lors d'un acccident nucleaire. Le memoire examine les limitations des dosimetres a film et expose les circonstances accompagnant certains accidents, lesquelles demontrent la necessite de prevoir un programme efficace de dosimetrie dans les installations ou des accidents nucleaires risquent de se produire. Lors de la mise au point d'un tel programme, il convient d'etudier certains parametres fondamentaux, a savoir: a) une methode permettant de trier les membres du personnel victimes d'un accident nucleaire; b) un systeme fixe (dispositif primaire) capable de determiner, avec un degre d'exactitude convenu la dose de premier choc a son emplacement meme; c) la necessite de disposer d''appareils secondaires'; d) la necessite de munir le personnel d'un dispositif donnant des indications sur le spectre et le flux afin de faciliter l'extrapolation de la dose en permettant de passer du dispositif fixe a l'emplacement de la personne exposee. La cellule de detection neutronique du systeme devrait renseigner sur le flux et le spectre, de maniere a obtenir des indications qualitatives appropriees dans l'evaluation de la dose. Les degres d'exactitude devront etre fixes d'apres l'etat actuel des connaissances. D'autre part, la cellule de detection gamma devrait permettre de mesurer ce rayonnement dans les limites des intensites d'interet biologique, soit entre 10 et 10{sup 3}r. Pour qu'un systeme de dosimetrie en cas d'accident soit efficace, le nombre d'appareils doit etre suffisant et leur emplacement bien choisi ; il faut aussi pouvoir les recuperer facilement. Si ces conditions sont remplies, on doit obtenir des donnees satisfaisantes sur toute l'etendue du spectre de fission. (author) [Spanish] La finilidad de un programa eficaz de dosimetria es la evaluacion de la dosis de neutrones y rayos gamma resultante de un accidente nuclear. A este respecto, el autor examina las limitaciones que presenta el dosimetro de pelicula, y trata ademas de la experiencia adquirida con ocasion de determinados accidentes nucleares, experiencia que ha demostrado la necesidad de establecer un programa eficaz de dosimetria en las instalaciones en que no se excluya la posibilidad de que se produzcan accidentes de esta clase. Para establecer un programa eficaz de esta indole deben tenerse en cuenta varios parametros fundamentales, a saber: a) un metodo para clasificar las victimas del accidente nuclear; b) una instalacion dosimetrica fija (sistema primario) capaz de determinar in situ la dosis de primer impacto con un grado de exactitud previamente establecido; c) la necesidad de disponer de 'aparatos secundarios', y d) la necesidad de proveer al personal de dosimetros individuales que proporcionen informacion sobre el flujo y sobre el espectro, para facilitar la extrapolacion de los datos dosimetricos procedentes del sistema de dosimetros fijos, a los lugares ocupados por esas personas. La celda de deteccion neutronica del sistema debe informar sobre el flujo y el espectro a fin de proporcionar indicaciones cualitativas adecuadas para la evaluacion de la dosis. El grado de exactitud se fijara segun el estado actual de los conocimientos. Por otra parte, la celda de deteccion gamma debera permitir la medicion de las radiaciones gamma dentro del intervalo de interes biologico, esto es, entre 10 y 10{sup 3}r. Para que un sistema de dosimetria en caso de accidente sea eficaz, el numero de aparatos debe ser suficiente y su emplazamiento bien escogido; asimismo, es preciso poder recuperarlos rapidamente. El autor estima que una vez satisfechas esas condiciones, debe ser posible acopiar datos adecuados para todo el espectro de fision. (author) [Russian] Naznachenie jeffektivnoj dozimetricheskoj programmy, osushhestvljaemoj vo vremja jadernyh avarij, sostoit v obespechenii vozmozhnosti ocenki gamma- i nejtronnoj doz vo vremja jadernoj avarii. V jetoj svjazi obsuzhdaetsja vopros ob ogranichenii primenenija plenochnyh dozimetrov, v dopolnenie k nekotorym sluchajam avarij, kotorye ukazyvajut na njoobhodimost' imet' bolee jeffektivnuju programmu sistemy avarijnoj dozimetrii na ustanovkah, podverzhennyh opasnosti vozniknovenija jadernyh avarij. Pri razrabotke jeffektivnoj programmy, osushhestvljaemoj vo vremja jadernyh avarij, sleduet rassmotret' nekotorye osnovnye momenty, a imenno: a) metod zashhity personala, imejushhego otnoshenie k jadernym avarijam, b) ustanovlennaja sistema (pervichnyj blok), sposobnaja opredeljat' pervuju dozu stolknovenija v predelah opredelennoj stepeni tochnosti v meste raspolozhenija, s) neobhodimost' v ''vtorichnyh blokah'', i d) neobhodimost' v pribore, kotoryj personal imeet pri sebe i kotoryj obespechival by informaciju otnositel'no spektra i potoka s cel'ju okazanija pomoshhi v jekstrapoljacii dozy ot ustanovlennogo bloka do mestonahozhdenija cheloveka. Nejtronnyj komponent sistemy dolzhen obespechit' poluchenie informacii o potoke i spektre s cel'ju vyvedenija sootvetstvujushhih kachestvennyh kojefficientov pri ocenke dozy. Stepen' tochnosti dolzhna ustanavlivat'sja na osnove dostignutogo urovnja v rabote. Gamma- komponent sistemy dolzhen davat' vozmozhnost' provodit' izmerenie gamma-izluchenija v predelah biologicheskoj zony, predstavljajushhej interes, t .e . ot 10 do 10{sup 3} rentgen. Soobrazhenie otnositel'no chisla, razmeshhenija i legkosti obnaruzhenija avarijnyh blokov sostavljajut po sushhestvu neot{sup e}mlemuju chast' jeffektivnoj sistemy avarijnoj dozimetrii. Jeti soobrazhenija dolzhny obespechit' poluchenie v razumnyh predelah dannyh po vsemu spektru delenija. (author)}
place = {IAEA}
year = {1965}
month = {Jun}
}