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Leven, D.; Wendling, R.D.; Wurtinger, W.
Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Koeln (Germany, F.R.)
Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Koeln (Germany, F.R.)
AbstractAbstract
[en] It is the aim of this paper to fixe the basis for constituting safety requirements in research reactors as well as to list priorities allowing the analysis of research reactors with respect to maybe necessary backfitting measures. Therefore, the research reactors have been attached to different system groups and risk groups. The criteria leading to this classification are based on the evaluation of the requirements to the systems for controlling the after-heat removal, and on the evaluation of the hazards potential of the reactors. It could be showed that all research reactors in the German Federal Republic can be classified into three system groups and three risk groups. The results of the classification into these groups have been put into relation; this leads to a sequence of the stages for the necessary safety requirements as well as to a listing of priorities allowing the analysis of research reactors with respect to maybe necessary backfitting measures. The group with highest requirements and highest priority includes 10% of the investigated research reactors; the group with next lower requirements and second priority includes 23%. 67% are to be classified in the group with lowest requirements and third priority. (orig.)
[de]
Ziel des Berichtes ist es, eine Basis zu schaffen fuer zu erstellende Sicherheitsanforderungen an Forschungsreaktoren und fuer die Aufstellung einer Prioritaetenliste, nach der die Analysen der Forschungsreaktoren im Hinblick auf eventuell zu treffende Backfitting-Massnahmen vorgenommen werden koennen. Hierzu wurden den Forschungsreaktoren Systemgruppen und Gefaehrdungsgruppen zugeordnet. Die Kriterien, nach denen diese Zuordnung erfolgt, basieren auf einer Bewertung der Anforderungen an die Systeme zur Beherrschung der Nachwaermeabfuhr und auf eine Bewertung des Gefaehrdungspotentials der Reaktoren. Es zeigte sich, dass alle Forschungsreaktoren in der Bundesrepublik Deutschland drei Systemgruppen und drei Gefaehrdungsgruppen zugeordnet werden koennen. Die Ergebnisse der Zuordnung nach diesen Gruppen wurden miteinander in Beziehung gesetzt; daraus ergibt sich sowohl eine Skalierung der Anforderungsstufen fuer zu erstellende Sicherheitsanforderungen als auch eine Prioritaetenliste, nach der die Analyse der Forschungsreaktoren im Hinblick auf evenutuell zu treffende Backfitting-Massnahmen vorgenommen werden koennte. In die Gruppe mit den hoechsten Anforderungen und der hoechsten Prioritaet fallen 10% der untersuchten Forschungsreaktoren; in die Gruppe der naechst niedrigeren Anforderungen und der 2. Prioritaet gehoeren 23% der untersuchten Forschungsreaktoren. 67% sind der Gruppe mit niedrigsten Anforderungen und der 3. Prioritaet zuzuordnen. (orig.)Original Title
Backfitting-Forschungsreaktoren. T. 1
Primary Subject
Source
Oct 1981; 19 p
Record Type
Report
Report Number
Country of publication
Publication YearPublication Year
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Gruendler, D.; Wurtinger, W.
Presentation of topical GRS papers. GRS expert discussion meeting 1990: Reactor safety - an international task
Presentation of topical GRS papers. GRS expert discussion meeting 1990: Reactor safety - an international task
AbstractAbstract
[en] The PC-based program explained by the paper is a program for the characterization and monitoring of nuclear power plant wastes which has been developed for implementing the regulation issued by the BMU. The program system's module for declaration and monitoring of the radionuclide inventory, MOPRO, is explained in detail. (DG)
[de]
Zur Umsetzung der Richtlinie des BMU wurde fuer KKW-Abfaelle ein PC-Programm, das Abfallfluss-Verfolgungs- und Kontrollsystem (AVK), entwickelt. Bestandteil des AVK ist das Modul zur Deklaration und Pruefung des Nuklidinventars der erfolgten Abfaelle (MOPRO). Das Modul zur Nukliddeklaration wird beschrieben. (DG)Original Title
Deklaration und Pruefung des Radionuklidinventars radioaktiver Abfaelle im Rahmen der Abfallflusskontrolle
Primary Subject
Secondary Subject
Source
Gesellschaft fuer Reaktorsicherheit mbH (GRS), Koeln (Germany); 111 p; 1990; p. 1-13; GRS special meeting: Reactor safety - an international assignment; GRS-Fachgespraech: Reaktorsicherheit - Eine Internationale Aufgabe; Cologne (Germany); 7-8 Nov 1990; Available from FIZ Karlsruhe
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Publication YearPublication Year
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INIS VolumeINIS Volume
INIS IssueINIS Issue
Baltes, B.; Gruendler, D.; Holzhauer, U.; Mielke, H.; Wurtinger, W.
Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Koeln (Germany, F.R.); Bundesministerium fuer Umwelt-, Naturschutz und Reaktorsicherheit, Bonn (Germany, F.R.)
Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Koeln (Germany, F.R.); Bundesministerium fuer Umwelt-, Naturschutz und Reaktorsicherheit, Bonn (Germany, F.R.)
AbstractAbstract
[en] The report summarizes the results of the meeting by comparing main aspects of the strategies and the conditions in the two countries. The aspects discussed are operational safety analysis programmes for repositories, repository design and performance analysis, waste package design and performance testing, long-term, post closure and safety assessment for LAW, TRU, HAW, and spent fuel. The meeting gathered representatives of the BMU/GRS and of the Office of Civilian Radioactive Waste Management (OCRWM) of the DOE. (DG)
[de]
Der Bericht fasst die Ergebnisse eines Erfahrungsaustausches ueber das amerikanische Entsorgungskonzept, die Sicherheitsanalyse der Betriebsphase, Endlagerbedingungen, Produktkontrolle und die Langzeitsicherheit fuer LAW, TRU, HAW und Spent Fuel zusammen. Gespraechspartner sind Mitglieder des BMU/GRS sowie des OCRWM des DOE. Die abweichende Vorgehensweise vom bundesdeutschen Konzept wird herausgestellt. (DG)Original Title
Unterschiede zwischen amerikanischen und deutschen Endlagerstrategien
Primary Subject
Source
Schriftenreihe Reaktorsicherheit und Strahlenschutz; May 1987; 43 p; GRS-A--1355; CONTRACT BMU SR 389; BMU SR 390; 84 500; 84 555; Available from GRM Werbeberatung - Werbemittlung - PR, Eggenstein-Leopoldshafen, (Germany, F.R.)
Record Type
Report
Report Number
Country of publication
DEVELOPED COUNTRIES, ELEMENTS, FUEL ELEMENTS, FUNCTIONAL MODELS, MANAGEMENT, MATERIALS, NATIONAL ORGANIZATIONS, NORTH AMERICA, NUCLEAR FACILITIES, PILOT PLANTS, RADIOACTIVE MATERIALS, RADIOACTIVE WASTE FACILITIES, RADIOACTIVE WASTES, REACTOR COMPONENTS, US DOE, US ORGANIZATIONS, WASTE DISPOSAL, WASTE MANAGEMENT, WASTES
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AbstractAbstract
[en] The guideline of the Ministry for Environmental Protection for controlling radioactive waste with a negligible development of heat defines in detail what data are relevant to the control of radioactive waste and should be followed up on and included in a system of documentation. By introducing the AVK (product control system for tracing the course of waste disposal) the operators of German nuclear power plants have taken the requirements of this guideline into account. In particular, possibilities for determining the degree of radioactivity of radioactive waste, which the BMU-guidelines call for, were put into practice by means of the programming technology of the product control system's module MOPRO. (orig.)
[de]
Die BMU-Richtline zur Kontrolle radioaktiver Abfaelle mit vernachlaessigbarer Waermeentwicklung legt detailliert fest, welche Daten fuer die Kontrolle radioaktiver Abfaelle relevant und mittels eines Dokumentationssystems zu erfassen und zu verfolgen sind. Die Betreiber deutscher Kernkraftwerke haben mit der Einfuehrung des AVK diesen Anforderungen der Richtlinie Rechnung getragen. Insbesondere wurden auch die von der BMU-Richtlinie vorgesehenen Moeglichkeiten zur Bestimmung des Aktivitaetsgehaltes radioaktiver Abfaelle mittels des AVK-Moduls MOPRO programmtechnisch umgesetzt. (orig.)Original Title
Kontrolle radioaktiver Abfaelle
Primary Subject
Secondary Subject
Source
Laser, M.; Halaszovich, S. (comps.); Forschungszentrum Juelich GmbH (Germany). Zentralabteilung Forschungsreaktoren und Kerntechnische Betriebe; 168 p; May 1992; p. 94-110; Seminar on radioactive waste in the Federal Republic of Germany; Rheinsberg (Germany); 23 May 1991
Record Type
Report
Literature Type
Conference
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AbstractAbstract
[en] The safety requirements for waste barrels, waste products and containers contained in the final storage conditions were derived from the safety analysis for the specific site. The results of the fault case analysis were decisive for structuring these requirements. Based on the basic requirements, which are made of all waste barrels regardless of the activity inventory, the safety requirements rise with an increasing activity inventory of a waste barrel. These rising requirements are, however, structured so that the producer of the waste can choose between different combinations and can therefore look for the most suitable one for this waste. (orig.)
[de]
Die bei den Endlagerungsbedingungen enthaltenen sicherheitstechnischen Anforderungen an Abfallgebinde, Abfallprodukt und Behaelter wurden aus der standortspezifischen Sicherheitsanalyse abgeleitet. Massgebend fuer die Strukturierung dieser Anforderungen waren die Ergebnisse der Stoerfallanalyse. Basierend auf Grundanforderungen, die unabhaengig von Aktivitaetsinventar an alle Abfallgebinde gestellt werden, steigen die sicherheitstechnischen Anforderungen mit zunehmendem Aktivitaetsinventar eines Abfallgebindes. Dabei wurden diese steigenden Anforderungen jedoch so strukturiert, dass der Abfallverursacher zwischen verschiedenen Kombinationen, die alle die gleiche Sicherheit garantieren, waehlen und somit die fuer seine Abfaelle am besten geeignete aussuchen kann. (orig.)Original Title
Anforderungen an Abfallgebinde, Abfallprodukt and Abfallbehaelter
Primary Subject
Source
Warnecke, E.; Giller, H. (eds.); Physikalisch-Technische Bundesanstalt, Braunschweig (Germany, F.R.). Abt. Sicherstellung und Endlagerung Radioaktiver Abfaelle; 362 p; ISBN 3-88314-942-X; 
; Sep 1989; p. 11-31; 85. PTB seminar on product control of radioactive waste; 85. PTB-Seminar ueber Produktkontrolle Radioaktiver Abfaelle; Braunschweig (Germany, F.R.); 17-18 Jul 1989
; Sep 1989; p. 11-31; 85. PTB seminar on product control of radioactive waste; 85. PTB-Seminar ueber Produktkontrolle Radioaktiver Abfaelle; Braunschweig (Germany, F.R.); 17-18 Jul 1989
Record Type
Report
Literature Type
Conference
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Publication YearPublication Year
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INIS IssueINIS Issue
AbstractAbstract
[en] Using the results from nuclide specific activity measurements of the primary coolant and of radioactive wastes in German and American PWR and BWR, a correlation anaylsis was performed to determine the relationship between reference nuclides relevant to nuclear power plants and the key nuclides Co-60 and Cs-137. The analysis showed that the radionuclides from normal operation wastes which are required to be declared can be correalted to the above mentioned key nuclides. A PC code was developed on the basis of the correlation parameters derived from the analysis. This code allows a simple and practical calculation of the nuclide inventory of nuclear power plant wastes. All that is required is the knowledge of the activity of easily measurable key nuclides in the waste. This code will be integrated in the AVK system, the wasteflow, pursuit and product control system, as an individual calculatory module. (orig.)
Primary Subject
Source
Warnecke, E. (Bundesamt fuer Strahlenschutz, Salzgitter (Germany, F.R.)); Odoj, R. (Forschungszentrum Juelich GmbH (Germany, F.R.)); Simon, R. (Commission of the European Communities, Brussels (Belgium)) (eds.); Bundesamt fuer Strahlenschutz, Salzgitter (Germany, F.R.); BfS Schriften; no. 1/90; 741 p; 1990; p. 701-716; 2. international seminar on radioactive waste products: Requirements for waste acceptance and quality control; Juelich (Germany, F.R.); 28 May - 1 Jun 1990; Available from FIZ Karlsruhe
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CESIUM ISOTOPES, CHEMICAL ANALYSIS, COBALT ISOTOPES, ENRICHED URANIUM REACTORS, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MANAGEMENT, MATERIALS, MINUTES LIVING RADIOISOTOPES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, OPERATION, POWER REACTORS, RADIOACTIVE MATERIALS, RADIOACTIVE WASTES, RADIOISOTOPES, REACTORS, SPECTROSCOPY, THERMAL REACTORS, WASTE MANAGEMENT, WASTES, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
Publication YearPublication Year
Reference NumberReference Number
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INIS IssueINIS Issue
Gruendler, D.; Wurtinger, W.
Waste management '87: Waste isolation in the US, technical programs, and public education
Waste management '87: Waste isolation in the US, technical programs, and public education
AbstractAbstract
[en] Waste packages for disposal in a repository in the Federal Republic of Germany have to meet safety requirements derived from site specific safety analyses. The examination of the waste packages with regard to compliance with these requirements is the main objective of quality control measures. With respect to quality control the requirements have to be specified in a way that practicable control measures can be applied. This is dealt with for the quality control of the activity inventory and the quality control of the waste form. The paper discusses the determination of the activity of hard-to-measure radionuclides and the specification of safety related requirements for the waste form and the packaging using typical examples
Primary Subject
Secondary Subject
Source
Post, R.G; p. 135-140; 1987; p. 135-140; University of Arizona Nuclear Engineering Dept; Tucson, AZ (USA); Waste management '87; Tucson, AZ (USA); 1-5 Mar 1987
Record Type
Book
Literature Type
Conference
Country of publication
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AbstractAbstract
No abstract available
Source
International conference on the applications of the Moessbauer effect; Bendor, France; 02 Sep 1974
Record Type
Journal Article
Literature Type
Conference
Journal
J. Phys. (Paris), Colloq; (no.6); p. 581-587
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AbstractAbstract
[en] The up-to-date unknown Moessbauer effect of the 5/2-1/2 E2 transition at 158.4keV in 199Hg was observed using the current integration technique. Hg-Pt alloys in the concentration range up to 65at.% mercury at 4.2K were investigated. For mercury concentrations <1% the alloy system shows a relatively small weakening of the impurity-to-host binding at low mercury concentrations, resulting in a Debye temperature thetasub(D)=211+-4K. Between 20 and 65at.%Hg there exist two intermetallic mercury compounds, HgPt and Hg2Pt. The latter shows a quadrupole splitting in the Moessbauer spectra
Source
International conference on the applications of the Moessbauer effect; Corfu, Greece; 13 - 17 Sep 1976
Record Type
Journal Article
Literature Type
Conference
Journal
J. Phys. (Paris), Colloq; (no.6); p. C6.697-C6.701
Country of publication
Publication YearPublication Year
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AbstractAbstract
[en] The Moessbauer effect on the 158 keV 5/2- -1/2- transition in 199Hg, of the order of 10 ppm, has been studied using the current integration technique. The isomer shift between the Hg(I)- and Hg(II)-fluorides as well as the quadrupole splitting in Hg2Pt and Hg2F2 are interpreted in terms of relativistic Hartree-Fock-Slater and Molecular Orbital calculations. The following nuclear parameters could be derived: Δ[r2] = (3.2+-1.1) 10-3fm2 and Q(5/2-) = (-0.8+-0.4)b. Evidence for an oblate triaxially deformed 199Hg nucleus is derived from particle plus rotor calculations. (orig.)
Primary Subject
Source
Thesis of W. Wurtinger.
Record Type
Journal Article
Literature Type
Numerical Data
Journal
Z. Phys., A; v. 293(3); p. 219-227
Country of publication
ALLOYS, DATA, DATA FORMS, ENERGY LEVELS, EVEN-ODD NUCLEI, FLUORIDES, FLUORINE COMPOUNDS, GAMMA SPECTROMETERS, HALIDES, HALOGEN COMPOUNDS, HEAVY NUCLEI, INFORMATION, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MATHEMATICAL MODELS, MEASURING INSTRUMENTS, MERCURY COMPOUNDS, MERCURY ISOTOPES, MINUTES LIVING RADIOISOTOPES, NUCLEAR PROPERTIES, NUCLEI, NUMERICAL DATA, RADIOISOTOPES, SPECTROMETERS, STABLE ISOTOPES
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