You need JavaScript to view this

Nuclear Research Center Karlsruhe, Institute of Nuclear Waste Management Technology. Progress report on research and development activities in 1993; Kernforschungszentrum Karlsruhe, Institut fuer Nukleare Entsorgungstechnik. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1993

Technical Report:

Abstract

Priority subjects of the Institute of Nuclear Waste Management Technology` work in 1993 were: Corrosion studies of high burnup LWR fuel in interaction with brines; retention of Pu, A Np and Tc curing corrosion of the high-level radioactive glass R7T7; formation of hydrotalcite during corrosion of the simulated inactive glass R7Z7 in brines; chemical behaviour of redox sensitive elements in aqueous chloride-containing systems in the near range of repositories; corrosion studies of waste container materials; solid-liquid equilibriums of uranium compounds in concentrated brines; thermodynamics of Np(V) in concentrated brines; quantification of radiation-chemical effects in the near range of repositories with a view to redox state change and gas formation; laser-spectroscopic speciation and thermodynamics of Cm(III) in highly concentrated brines; development of laser-spectroscopic speciation methods; radio-chemical and chemical analyses of redioactive samples; theoretical work on the development of a sorption model; studies of the compaction behaviour of filling material; thermomechanic effects of an HAW storage site on neighbouring inhomogeneities in the salt rock; optimization of vitrification technologies; structural studies of HAW model glasses. (orig./HP) [Deutsch] Schwerpunkte der Institutsarbeiten im Jahr 1993 waren: Korrosionsuntersuchungen an hochabgebranntem LWR-Kernbrennstoff in Wechselwirkung mit Salzloesungen; Rueckhaltung von Pu, Am, Np und Tc bei der Korrosion des  More>>
Publication Date:
Mar 01, 1994
Product Type:
Technical Report
Report Number:
KFK-5333
Reference Number:
SCA: 052000; PA: DEN-94:0FN380; EDB-95:012591; SN: 95001306082
Resource Relation:
Other Information: PBD: Mar 1994
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; RADIOACTIVE WASTE DISPOSAL; KERNFORSCHUNGSZENTRUM KARLSRUHE; RADIOACTIVE WASTE PROCESSING; PROGRESS REPORT; HIGH-LEVEL RADIOACTIVE WASTES; UNDERGROUND DISPOSAL; SALT CAVERNS; GLASS; VITRIFICATION; CORROSION; TRANSURANIUM ELEMENTS; CONTAINERS; RESEARCH PROGRAMS; CHEMICAL REACTIONS; 052000; WASTE MANAGEMENT
OSTI ID:
10105657
Research Organizations:
Kernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Nukleare Entsorgungstechnik
Country of Origin:
Germany
Language:
German
Other Identifying Numbers:
Journal ID: ISSN 0303-4003; Other: ON: DE95726740; TRN: DE94FN380
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
DEN
Size:
22 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

None. Nuclear Research Center Karlsruhe, Institute of Nuclear Waste Management Technology. Progress report on research and development activities in 1993; Kernforschungszentrum Karlsruhe, Institut fuer Nukleare Entsorgungstechnik. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1993. Germany: N. p., 1994. Web.
None. Nuclear Research Center Karlsruhe, Institute of Nuclear Waste Management Technology. Progress report on research and development activities in 1993; Kernforschungszentrum Karlsruhe, Institut fuer Nukleare Entsorgungstechnik. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1993. Germany.
None. 1994. "Nuclear Research Center Karlsruhe, Institute of Nuclear Waste Management Technology. Progress report on research and development activities in 1993; Kernforschungszentrum Karlsruhe, Institut fuer Nukleare Entsorgungstechnik. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1993." Germany.
@misc{etde_10105657,
title = {Nuclear Research Center Karlsruhe, Institute of Nuclear Waste Management Technology. Progress report on research and development activities in 1993; Kernforschungszentrum Karlsruhe, Institut fuer Nukleare Entsorgungstechnik. Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1993}
author = {None}
abstractNote = {Priority subjects of the Institute of Nuclear Waste Management Technology` work in 1993 were: Corrosion studies of high burnup LWR fuel in interaction with brines; retention of Pu, A Np and Tc curing corrosion of the high-level radioactive glass R7T7; formation of hydrotalcite during corrosion of the simulated inactive glass R7Z7 in brines; chemical behaviour of redox sensitive elements in aqueous chloride-containing systems in the near range of repositories; corrosion studies of waste container materials; solid-liquid equilibriums of uranium compounds in concentrated brines; thermodynamics of Np(V) in concentrated brines; quantification of radiation-chemical effects in the near range of repositories with a view to redox state change and gas formation; laser-spectroscopic speciation and thermodynamics of Cm(III) in highly concentrated brines; development of laser-spectroscopic speciation methods; radio-chemical and chemical analyses of redioactive samples; theoretical work on the development of a sorption model; studies of the compaction behaviour of filling material; thermomechanic effects of an HAW storage site on neighbouring inhomogeneities in the salt rock; optimization of vitrification technologies; structural studies of HAW model glasses. (orig./HP) [Deutsch] Schwerpunkte der Institutsarbeiten im Jahr 1993 waren: Korrosionsuntersuchungen an hochabgebranntem LWR-Kernbrennstoff in Wechselwirkung mit Salzloesungen; Rueckhaltung von Pu, Am, Np und Tc bei der Korrosion des hochaktiven Glases R7T7; Bildung von Hydrotalkit bei der Korrosion des inaktiv simulierten Glases R7T7 in Salzloesungen; Chemisches Verhalten von redoxsensitiven Elementen in waessrigen chloridhaltigen Systemen des Endlagernahbereiches; Korrosionsuntersuchungen an Abfallbehaeltermaterialien; Fest-fluessig-Gleichgewichte von Uranverbindungen in konzentrierten Salzloesungen; Thermodynamik von Np(V) in konzentrierten Salzloesungen; Quantifizierung strahlenchemischer Effekte im Endlagernahbereich im Hinblick auf Redoxzustandsaenderung und Gasbildung; Laserspektroskopische Speziation und Thermodynamik von Cm(III) in hochkonzentrierten Salzloesungen; Entwicklung laserspektroskopischer Speziationsmethoden; Radiochemische und chemische Analyse radioaktiver Proben; Theoretische Arbeiten zur Entwicklung eines Sorptionsmodells; Untersuchungen zum Kompaktierungsverhalten von Versatzmaterial; Thermomechanische Auswirkung eines HAW-Lagerfeldes auf die benachbarten Inhomoginitaeten im Salzgebirge; Optimierung der Verfahrenstechnik zur Verglasung; Strukturuntersuchungen an HAW-Modellglaesern. (orig./HP)}
place = {Germany}
year = {1994}
month = {Mar}
}