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Decitre, J.L.
8. International congress of the International Radiation Protection Association (IRPA8)1992
8. International congress of the International Radiation Protection Association (IRPA8)1992
AbstractAbstract
[en] The specific activity limits for beta-gamma emitters toward the decontamination of steel used in G2 and G3 Uranium Natural Graphie Gas reactors are: 1 Bq/g and Bq/cm2. The principle radionuclides are Co 60, its deposit accounts for 95% of deposits and encrustations on the steel pipes. About 90% of the steel from the dismantling can be reused. A brief history of the reactors and the dismantling methods are provided in the paper
Original Title
Traitement des aciers contamines en provenance des reacteurs UNGG G2 et G3 en vue d'une reutilisation dans le domaine industriel
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Source
International Radiation Protection Association, Montreal, Quebec (Canada); 2 v; ISBN 1-55048-657-8;
; 1992; (v.2) p. 1428-1431; 8. international congress of the International Radiation Protection Association (IRPA8); Montreal, Quebec (Canada); 17-22 May 1992; 1 fig.

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AbstractAbstract
No abstract available
Original Title
Maximisation du taux de combustion moyen en pile dans un reacteur a uranium naturel avec cheminement axial bi-directionnel du combustible
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Journal Article
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Progress Report
Journal
Industries Atomiques; v. 14(11-12); p. 23-27
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Meshik, A.P.; Kehm, K.; Hohenberg, C.M.
Washington Univ., St. Louis, MO (United States)2000
Washington Univ., St. Louis, MO (United States)2000
AbstractAbstract
[en] In situ laser extraction techniques were applied for the study of heavy noble gases in a polished section of Zone 13 from the natural nuclear reactor in Okelobondo. Three main mineral phases were identified in this polished section using SEM-EDX. The Xe and Kr isotopic structures were determined by multiple measurements in each of these phases. Twenty-four isotopic analyses of the gases extracted from two different U-rich phases revealed nearly normal fission spectra. All 9 analyses of a U-free phase, consisting mainly of alumophosphates, demonstrated an unusual isotopic composition (136Xe/134Xe/132Xe/131Xe/130Xe129Xe/128Xe = 1/1.25/1.73/0.89/0.0045/0.274/0) with concentrations ranging up to 10-2 cm3 STP/g. This is the highest Xe concentration ever measured in a natural material. Kr was also anomalous, although to a lesser extent. These results confirm the presence of Chemical Fractionation of Fission Xe (CFF-Xe) in the Okelobondo alumophosphates. CFF-Xe is a decay product of intermediate fission fragments that have migrated out of the U-rich host phases into adjacent U-free minerals. The CFF-Xe spectra in the alumophosphates are also accompanied by 130Xe excesses, which are attributed to neutron capture on fissiogenic 129I that apparently migrated out of the nearby U-rich minerals. The 130Xe/129Xe ratio allows one to estimate the thermal equivalent neutron dose of 1.1 x 1021 n/cm2. The presence of an unknown fission component remarkably similar in composition to CFF-Xe can be inferred from the atmospheric and terrestrial data. This leads one to the hypothesis that the CFF process has operated on a global scale on the Earth
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AbstractAbstract
[en] The moderator integral and differential worth as a function of moderator level in the core of NRX/CIR type reactor has been determined using standard computer codes WIMSD/4 and CITATION. The core reactivity without any moderator was calculated to be about -1096 mk whereas the moderator level of 306 cm adds a total of about 1140 mk reactivity in the core. (author)
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Journal Article
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Science International (Lahore); ISSN 1013-5316;
; v. 18(2); p. 119-120

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AbstractAbstract
No abstract available
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Transactions of the American Nuclear Society 1977 annual meeting; New York, NY, USA; 12 Jun 1977; Published in summary form only.
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Journal Article
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Transactions of the American Nuclear Society; v. 26 p. 305-306
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No abstract available
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85. annual meeting of the Mining Society of Nova Scotia; Ingonish Beach, Nova Scotia, Canada; Jun 1972; 8 refs.
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Journal Article
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Conference
Journal
CIM (Can. Min. Metall.) Bull; v. 65(727); p. 89-92
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McCriric, H.
AB Atomenergi, Stockholm (Sweden)1958
AB Atomenergi, Stockholm (Sweden)1958
AbstractAbstract
[en] Starting with the known reactor constants for a heavy water moderated reactor with reflector and a given number of control rods of a certain size, the reactivity equivalence of the control rods is calculated. The calculation is given in detail. The number, length and diameter of the control rods is then varied and the effect of these parameters on the reactivity is shown graphically. Flux plots are also given for the reactor with and without control rods
Primary Subject
Source
May 1958; 28 p; 2 refs., 10 figs.
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Report
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Millar, C.
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
Nuclear energy maturity. Communications of the I. European nuclear conference. Paris, 21-25 April 19751975
AbstractAbstract
[en] Fuel management schemes and fueling patterns chosen for CANDU-type reactors are presented. The problems encountered during refueling are underlined
[fr]
On presente les plans de gestion du combustible et les types de chargement adoptes pour les differentes centrales du type CANDU. On souligne les problemes rencontres lors des rechargementsOriginal Title
La gestion du combustible des reacteurs CANDU
Primary Subject
Source
Lehoulier, J.; Mantega, M. (eds.); American Nuclear Society, Hinsdale, Ill.; Societe Europeenne d'Energie Nucleaire, Petit-Lancy (Switzerland); p. 139-140; 1975; Societe Francaise de l'Energie Nucleaire; Clamart, France; 1. European nuclear conference; Paris, France; 21 Apr 1975
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Book
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Conference
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AbstractAbstract
[en] CANDU reactors are studied with methods of integrated analysis using normative econometric models. (authors)
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AbstractAbstract
[en] The impact of neutron leakage form a core on core burnup and reactivity consumption rate (mk/EFPD) was analyzed. The two cores with different diffusion characteristics but having the same specific power (MWth/kg-U) were chosen and analyzed. It was found that the core with higher diffusion characteristics has higher reactivity consumption rate and smaller cycle length. (author)
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Journal Article
Journal
Science International (Lahore); ISSN 1013-5316;
; v. 18(2); p. 125-126

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