Volume 1265 Symposium AA – Scientific Basis for Nuclear Waste Management XXXIV 2010, 1265-AA06-03 Seismic Tomography Investigation in 140m Gallery in the Horonobe URL Project. Volume 1265 Symposium AA – Scientific Basis for Nuclear Waste Management XXXIV 2010, 1265-AA09-08 Performance Indicators Quantifying the Contribution of Safety Functions to the Confinement of Radionuclides in a Geological Repository System Eef Weetjensa1, Jan Marivoeta2and Suresh C. Seetharam.
2014 Scientific Basis for Nuclear Waste Management XXXVII. MRS Proceedings Volume 1665, 111-116. Valls, A., Grivé, M., Riba, O., Morales, M. and Spahiu, K. Estimation of the long term helium production in high burn-up spent fuel due to alpha decay and consequences for the canister. 2014 Scientific Basis for Nuclear Waste Management XXXVII. Scientific Basis for Nuclear Waste Management XXXIV. Symposium Proceedings, San Fransisco, United States, 5-9 April 2010 / MRS, Warrendale, PA, United States, Materials Research Society.
Volume 1265 Symposium AA – Scientific Basis for Nuclear Waste Management XXXIV 2010, 1265-AA06-11 Structure and alteration kinetics of rare-earth rich borosilicate glasses with 64 – 2x SiO 2 / 18 B 2 O 3 / 18 Na 2 O / x RE2O 3 composition RE = Y or Eu La. Symposium LL, 'Scientific Basis for Nuclear Waste Management XXXVI', was held November 25-30 at the 2012 MRS Fall Meeting in Boston, Massachusetts. This Symposium continues to set the research agenda in the field of radioactive waste management, charting the development of waste processing, conditioning, packaging and disposal. Get this from a library! Scientific basis for nuclear waste management XXXIV: Spring 2010, April 5-9, San Francisco, California, U.S.A. [Katherine L Smith; Materials Research Society. Fall Meeting;]. Effect of Ionic Strength on the Stability of Colloids Released from Injection Grout Silica Sol - Volume 1265 - Pirkko L Holtta, Mari Lahtinen, Martti Hakanen, Jukka Lehto, Piia Juhola. In: Scientific Basis for Nuclear Waste Management XXXIV. Symposium Proceedings, San Fransisco, United States, 5-9 April 2010 / MRS, Warrendale, PA, United States, Materials Research Society, 2010, p. 191-196 Yu L., Batlle F., lloret A.- A coupled model for.
3. The parameters Vm and n of the adsorption iso- therm, predicted by the present formulas, can be used to obtain approximate information about the surface area, pore volume, and pore-size dis- tribution on the basis of a given w/c, curing time, cement type, and temperature. This is useful for cases where the adsorption test data are unavail. MRS 2011 35th International Symposium on Scientific Basis for Nuclear Waste Management Buenos Aires Argentina MRS symposium proceedings Vol.1475 pp.545-550 2012 2011.
Scientific Basis for Nuclear Waste Management XXXIV. Symp. Proc. Volume 1265. 1265-AA09-09 Results of microbiological and geochemical sampling in the Outokumpu deep 2.5 km borehole are. 1265-1269 2008. Kanchanarat, N. 30th Symposium on Scientific Basis for Nuclear Waste. 2006 Boston MA. Source: SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXX Volume: 985 Pages: 353-358.
Feb 01, 1999 · Table 2, modified from Krivenko, summarizes the numerous applications of alkali-activated cements up to the present.Alkali-activated cements have found a variety of applications, particularly since the 1970s, such as agricultural, industrial, residential, transportation e.g., railway ties, mining, various high-volume applications, oil well cements, and water stop or sealing applications. Kazuya Idemitsu, Daisuke Akiyama, Akira Eto, Yoshihiko Matsuki, Yaohiro Inagaki, Tatsumi Arima, Migration Behavior of Alkali Earth Ions in Compacted Bentonite with Iron Corrosion Product Using Electrochemical Method, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXIV, Vol.1265, pp.227-232. Kazuya IDEMITSU, Daisuke AKIYAMA, Akira ETO, Yoshihiko MATSUKI, Yaohiro INAGAKI, Tatsumi ARIMA, Migration Behavior of Alkali Earth Ions in Compacted Bentonite with Iron Corrosion Product Using Electrochemical Method, Proceedings of Materials Research Society Symposium Vol.1265 Scientific Basis for Nuclear Waste Management XXXIV, pp.227-232. Scientific basis for nuclear waste management XIV, International Symposium on the Scientific Basis for Nuclear Waste Management 1990: Boston, Mass., Materials Research Society. Scientific Basis for Nucl ear Waste Management XXXIV, edited by K.L. Smith. uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant WIPP.
Scientific Basis for Nuclear Waste Management XXX, Vol. 985 pp 145-150 Hyatt NC, Morgan S, Stennett MC, Scales CR & Deegan D 2007 Characterisation of plasma vitrified simulant plutonium contaminated material waste. Scientific Basis for Nuclear Waste Management. May 11, 2015 · Rebak, G. O. Ilevbare, and R. M. Carranza, “Repassivation potential of Alloy 22 in sodium and calcium chloride brines,” in Symposium Scientific Basis for Nuclear Waste Management XXXI, Materials Research Society Symposium Proceedings, Vol. 1107, pp. 511-518 MRS. Moss, M., and G. M. Haseman, 1983, A proposed model for the thermal conductivity of dry and water-saturated tuff: Proceedings, Scientific Basis for Nuclear Waste Management VII, Materials Research Society, v. 26, p. 967–974. Google Scholar. Titanate, zirconate, mixed titanate zirconate phases with fluorite and fluorite-related structures, and aluminate and ferrite phases with perovskite and garnet structures are surv. Research is in progress to incorporate nuclear waste in new matrices with high structural stability, resistance to thermal shock, and high chemical durability. Interactions with water are important for materials used as a containment matrix for the radio nuclides. It is indispensable to improve their chemical durability to limit the possible release of radioactive chemical species, if the.
Jan 01, 2014 · Selection and peer-review under responsibility of the scientifi c committee of SumGLASS 2013 doi: 10.1016/j.mspro.2014.10.011 ScienceDirect 2nd International Summer School on Nuclear Glass Wasteform: Structure, Properties and Long- Term Behavior, SumGLASS 2013 A Thermodynamic Approach to predict the Metallic and Oxide Phases Precipitations in. considering the need to develop, with scientific basis,. It also includes data on the in utero exposure of 1265 subjects at Hiroshima. the waste management in nuclear medicine departments. In the context of French nuclear waste vitrification, specific borosilicate glass waste forms are being developed to immobilize the large quantities >6 mol% of molybdenum and phosphorus 2 mol.
A comparison of the effects of alkali activation on the specific surface area of cementitious materials is illustrated in Table 2, which contrasts slag, one of the most important source materials for AAC with ordinary Portland cement.The results show that the surface area of granulated blast-furnace slag hydration product is enhanced to a much greater extent by alkali activation than is a. Full text of "Nuclear waste program: hearings before the Committee on Energy and Natural Resources, United States Senate, One hundredth Congress, first session.See other formats. Scientific Research Council and Pakistan Society of Scientific Research: Papers INTERNATIONAL REVIEW OF HUMANITIES & SCIENTIFIC RESEARCH 2016-20170.353, 2017-20180.581, 2018-20190.945, 2019-20201.220 2019 Indexed: 2519-5336: International Scientific Indexing ISI Papers INTERNATIONAL JOURNAL OF PUBLIC HEALTH AND CLINICAL SCIENCES. Nuclear Waste Management Strategies: An International Perspective presents worldwide insights into nuclear waste management strategies from a technical engineering perspective, with consideration for important legal aspects. Scientific basis for nuclear waste management XXXIV [electronic resource]: Spring 2010, April 5-9, San Francisco.
MRS Proceedings 2010,, 1265-AA02-01. DOI: 10.1557/PROC-1265-AA02-01. Dongjiang Yang, Zhanfeng Zheng, Yong Yuan, Hongwei Liu, Eric R. Waclawik, Xuebin Ke, Mengxia Xie, Huaiyong Zhu. Sorption induced structural deformation of sodium hexa-titanate nanofibers and their ability to selectively trap radioactive Raii ions from water. Phys. Chem. Chem. 137 Cs and 90 Sr, both byproducts of the fission process, make up the majority of high-level waste from nuclear power plants. 63 Ni is a byproduct of the erosion-corrosion process of the reactor components in nuclear energy plants. The concentrations of these ions in solution determine the Waste Class A, B, or C and thus selective removal of these ions over large excesses of other ions is. Sep 24, 2011 · Thus, an understanding of the relationships among brittleness, deformation behavior, and transport properties in mudstones is crucial for assessing the long‐term barrier function of mudstones in disposal repositories for radioactive waste.  Defined on the basis of specific rheological behavior [e.g., Dehandschutter et al., 2004, 2005. "selected pkoblcns of hazardous waste management in cal 1 forn i a —jafhjak y 1970" govi.rnors task forcl ktport of thfc hazardous wastes working group oh the governor s task force oh solid waste management»january 1970»44p.,pb- "tht technology oh solid waste management - implications -ok statfr policy" asstmlly scltncf and technology. Posiva, 2009. Nuclear Waste Management of the Olkiluoto and Loviisa Power Plants: Programme for Research, Development and Technical Design for 2010 – 2012, TKS-2009, Posiva Oy, Olkiluoto, Finland Tanskanen, J. 2007. Facility Description 2006. Posiva Oy, Eurajoki, Finland. Working Report 2007-21.
274 1992 NEPIS online LAI 20060421 hardcopy single page tiff environmental enforcement conference international waste environment legislation european member public information law commission eec compliance implementation countries citizens community directive 300R92012 PROCEEDINGS VOLUME II INTERNATIONAL CONFERENCE ON ENVIRONMENTAL ENFORCEMENT September. This banner text can have markup. web; books; video; audio; software; images; Toggle navigation.
In Section 134 of the Nuclear Waste Policy Act of 1982, 42 U.S.C. 10154, Congress specified a set of hybrid procedures for licensing expansions of spent fuel storage capacity at reactor sites. The process called for written submissions, oral argument, and an adjudicatory hearing only after specific findings by the Commission.
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