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Holdoway, K.A.
Union Carbide Corp., Oak Ridge, Tenn. (USA). Office of Waste Isolation1972
Union Carbide Corp., Oak Ridge, Tenn. (USA). Office of Waste Isolation1972
AbstractAbstract
[en] Rock salt was heated and irradiated in situ by implanted radioactive wastes during the Project Salt Vault experiment which was carried out at Lyons, Kansas, in the abandoned Carey Salt mine between 1965 and 1967. It was found that irradiation results in coloration of the salt, producing colors ranging from blue-black nearest the radiation source, to pale blue and purple farther from the source. Bleached areas are common in the radiation-colored salt, many representing trails produced by the migration of fluid inclusions towards the heat source. These visible trails are thought to have formed during the cooling down of the salt after the removal of the heaters and radiation sources. The distribution of primary structures in the salt suggests that little migration, if any, occurred during the course of the experiment. It is proposed that radiolysis of the brine within the inclusions may have led to the production of gases which impeded or prevented migration. Evidence of strain was observed in slip planes at 4 in. (10 cm) and between 5.5 and 10 in. (13.5 to 25.4 cm) from the array hole. Deformed bleached areas in the salt between the areas were slip planes are developed suggest that slight plastic deformation or flow may have occurred at 6 in. (15 cm) from the array hole. Differential thermal analysis shows that the maximum amount of stored energy also occurs at 6 in. (15 cm) from the array hole. This region may therefore represent the zone where the combined effect of stress and radiation was greatest
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30 Jun 1972; 74 p; Available from NTIS., PC A04/MF A01
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[en] Brief description of the concepts studied by partners; of the Molten Salt Fast Reactor Concept activities; of the activities on MOSART concept; and of activities on FHR concept.
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International Atomic Energy Agency, Nuclear Power Technology Development Section and INPRO Section, Vienna (Austria); vp; 15 Mar 2012; 11 p; 6. GIF-INPRO/IAEA Interface Meeting; Vienna (Austria); 6-7 Mar 2012; Also available on-line: https://www-legacy.iaea.org/INPRO/cooperation/6th_GIF_Meeting/presentations/MSR-Boussier.pdf
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[en] Feasibility study of an underground molten salt thorium reactor is presented. Fuel cycle and safety considerations are given. (TRA)
Original Title
Torium alapon mukodo, soolvadekos, fold ala telepitett atomreaktor lehetosege
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12 refs.
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[en] The underground exploration of a site with a view to its suitability for safe containment and final disposal of radioactive wastes (section 9a subsection 3 Atomic Energy Act) is not yet the beginning of an appropriate installation, and thus the plan approval procedure according to section 9 Atomic Energy Act is not required, this not even in the case of parts of the explored mine, such as shafts, after dimensioning and construction finding use in a final waste repository to be erected in the case of a positive decision on the site on the basis of a plan approval procedure. (Federal Administrative Court, judgment of 9.3.1990, BVerwG 7 G 23.89 (res judicata)). (orig./HP)
[de]
Die untertaegige Erkundung eines Standorts auf seine Eignung fuer die Sicherstellung und Endlagerung radioaktiver Abfaelle (Paragraph 9a Abs. 3 AtG) ist noch nicht der Beginn einer Errichtung einer entsprechenden Anlage und bedarf deshalb nicht der Planfeststellung nach Paragraph 9a AtG, das auch dann nicht, wenn Teile des Erkundungsbergwerks, wie z.B. die Schaechte, nach Dimensionierung und Bauausfuehrung im Falle positiver Standortentscheidung im dann aufgrund einer Planfeststellung zu errichtenden Endlager Verwendung finden sollen. Bundesverwaltungsgericht, Urteil vom 9.3.1990 BVerwG 7 C 23.89 (rechtskraeftig). (orig./HP)Original Title
Endlager Gorleben
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[en] Shapes made of salt are used as closures for horizontal or slightly inclined access roads to the hollow spaces. The sections are provided with precise, simple cross-sections for this purpose and are filled with cut shapes made of homogeneous salt to a length of several metres. The sections are then thermally melted at the intended places by heating pipes or laser beams. (PW)
[de]
Formkoerper aus Salzgestein dienen als Verschluss fuer horizontale oder schwach geneigte Zugangsstrecken zu Hohlraeumen. Dazu werden die Streckenabschnitte mit genauen einfachen Querschnitten versehen und mit geschnittenen Formkoerpern aus homogenem Salzgestein auf eine Laenge von mehreren Metern ausgefuellt. Die Strecken werden dann thermisch an vorgesehenen Stellen durch Heizleitungen oder Laserstrahlen verschmolzen. (PW)Original Title
Verfahren zur drucksicheren Einschliessung von Abfallstoffen, insbesondere radioaktiven Abfallstoffen, in Salzgestein
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24 Jul 1986; 21 May 1982; 2 p; DE PATENT DOCUMENT 3219080/C/; ?: 21 May 1982
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Patent
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[en] Volumetric and acoustic methods have been used to study the interactions of alkyl acetates with the ionic liquid 1-butyl-3-methylimidazolium chloride (bmim)(Cl) as a function of temperature. The density, ρ, and speed of sound, u, of methyl acetate, ethyl acetate and butyl acetate in aqueous 1-butyl-3-methylimidazolium chloride solutions have been measured in the temperature interval T = (288.15, 293.15, 298.15, 303.15 and 308.15) K and atmospheric pressure. In the present work, the apparent molar volumes (Vφ), limiting partial molar volumes (Voφ), transfer volumes at infinite dilution (Voφ), adiabatic compressibility (Kφ,s) limiting partial molar adiabatic compressibility (Koφ,s) and the infinite dilution partial molar expansibilities (φoE) along with Hepler’s constant values, (∂2V0φ/∂T2) of alkyl acetates in aqueous ionic liquid solution at the measured temperatures, have been reported. The results have been interpreted in terms of intermolecular interactions capable of existing within the mixture containing ionic liquid and the ester molecules. (author)
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Indian Journal of Pure and Applied Physics; ISSN 0019-5596;
; v. 53(7); p. 436-446

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Forsberg, Ch.W.; Renault, C.; Lebrun, C.; Ignatiev, V.
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2007
Societe Francaise d'Energie Nucleaire (SFEN), 75 - Paris (France)2007
AbstractAbstract
[en] In the last 5 years, there has been a rapid growth in interest in the use of high-temperature (700 to 1000 C degrees) molten and liquid fluoride salts as coolants and for other functions in nuclear systems. This interest is a consequence of new applications for high-temperature heat and the development of new reactor concepts. These salts have melting points between 350 and 500 C degrees; thus, they are of use only in high-temperature systems. Nitrate salts with a peak operating temperature of about 600 C degrees are the highest-temperature commercial liquid coolant available today; thus, the development of higher-temperature salts as coolants opens new nuclear and non-nuclear applications. These salts are being considered for intermediate heat transport loops between all types of high-temperature reactors (helium and salt cooled) and hydrogen production systems, oil refineries, and shale oil processing facilities. Historically, steam cycles with temperature limits of about 550 C degrees have been the only efficient method to convert heat to electricity. This limitation produced few incentives to develop high-temperature reactors for electricity production. However, recent advances in Brayton gas-turbine technology now make it possible to convert higher-temperature heat efficiently into electricity and thus have created the enabling technology for more efficient cost-effective high-temperature reactors. The near-term advanced high-temperature reactor (AHTR) uses a graphite-matrix coated-particle fuel and a liquid salt coolant. There is the longer-term potential of a liquid-salt-cooled fast reactor (LSFR) that uses metal-clad fuel and a liquid salt coolant. The molten salt reactor (MSR), with the fuel dissolved in the molten salt coolant, is receiving attention because of (1) the advancing salt-coolant technology and Brayton cycles that improve the economics, (2) advances in salt chemistry that enable the development of fast-spectrum MSRs with the safety advantages of large negative void coefficients, and (3) the interest in actinide burning where MSRs avoid the need to fabricate fuel of highly active actinides. Last, there is a developing interest in liquid-wall fusion machines with much higher power densities than solid-wall fusion machines. (authors)
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2007; 9 p; ICAPP 2007 - International congress on advances in nuclear power plants. The nuclear renaissance at work; Nice Acropolis (France); 13-18 May 2007; Available from: SFEN, 5 rue des Morillons, 75015 Paris (France); 17 refs.
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Diekmann, N.; Stuehrenberg, D.
Bundesanstalt fuer Geowissenschaften und Rohstoffe, Hannover (Germany); Bundesministerium fuer Forschung und Technologie, Bonn (Germany)1991
Bundesanstalt fuer Geowissenschaften und Rohstoffe, Hannover (Germany); Bundesministerium fuer Forschung und Technologie, Bonn (Germany)1991
AbstractAbstract
[en] According to the present planning level of the designed Gorleben repository, the salt produced by opening up cavities for ultimate disposal will be used as salt fines for backfilling residual cavities after radioactive waste emplacement. The essential function properties of the backfill - compaction and permeability - were studied for salt fines, and the results achieved were discussed. (BBR)
[de]
Nach dem derzeitigen Planungsstand fuer das projektierte Endlager Gorleben wird das bei der Auffahrung von Endlagerhohlraeumen anfallende Salz als Salzgrus zur Verfuellung der Resthohlraeume nach der Einlagerung radioaktiver Abfaelle verwendet werden. Die wesentlichen Funktionseigenschaften des Versatzes - Kompaktion und Permeabilitaet - wurden fuer Salzgrus untersucht und die erzielten Ergebnisse diskutiert. (BBR)Original Title
Untersuchungen zum Materialverhalten von Versatz unter Beruecksichtigung der Wechselwirkung Gebirge/Versatz und anderer Verschlusskomponenten in einem Endlager im Salinar
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Sep 1991; 74 p; CONTRACT BMFT KWA5801
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Sofronova, Yu.I.; Feofanova, M.A.; Evdokimov, A.N.; Kurzin, A.V., E-mail: eanchem@mail.ru
XXIII All-Russian conference of young chemical scientists (with international participation). Abstracts of reports2020
XXIII All-Russian conference of young chemical scientists (with international participation). Abstracts of reports2020
AbstractAbstract
No abstract available
Original Title
Primenenie geksaftorfosfata 1,3-dimetil-2-fenilimidazoliniya dlya razdeleniya dvojnykh azeotropnykh sistem
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Ministerstvo Nauki i Vysshego Obrazovaniya Rossijskoj Federatsii, Moscow (Russian Federation); Natsional'nyj Issledovatel'skij Nizhegorodskij Gosudarstvennyj Univ. im. N.I. Lobachevskogo, Nizhnij Novgorod (Russian Federation); 568 p; ISBN 978-5-91326-590-6;
; 2020; p. 443; 23. All-Russian conference of young chemical scientists (with international participation); XXIII Vserossijskaya konferentsiya molodykh uchenykh-khimikov (s mezhdunarodnym uchastiem); Nizhnij Novgorod (Russian Federation); 21-23 Apr 2020; 2 refs.

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No abstract available
Original Title
Zur Systematik untertaegiger Salzloesungsvorkommen im Kalibergbau
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Akademie der Wissenschaften der DDR, Leipzig. Zentralinstitut fuer Isotopen- und Strahlenforschung; 158 p; Nov 1983; p. 108; 3. workshop on isotopes in nature; Leipzig (German Democratic Republic); 15-18 Nov 1983; Published in summary form only.
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