Radiolysis and temperature effects in case of underground storage of bitumen
Description
On conservative assumptions limit values were determined for the specific activity in the bitumen products, which safely avoid under the conditions of storage in a nonventilated prototype cavity both the formation of a ignitable radiolytic gas/air mixture and intolerable heating of waste products over the entire storage time. Depending on the filling factor of the cavity and on the age of fixed fission products, the limit values of the specific activity in the waste products allowing to avoid an ignitable gas/air mixture in the cavity range from 0.09 Ci/l to 0.78 Ci/l. The respective limit values of specific activity allowing to avoid intolerable heating of wastes (> 700C) range form 0.3 Ci/l to 0.7 Ci/l, depending on the age of fission products and on type of filling. (orig.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (German)
Unter konservativen Annahmen wurden Grenzwerte fuer die spezifische Aktivitaet in Bitumenprodukten bestimmt, bei denen unter den Bedingungen der Lagerung in einer unbeluefteten Prototyp-Kaverne sowohl die Bildung eines zuendfaehigen Radiolysegas/Luft-Gemisches als auch eine unzulaessige Erwaermung der Abfallprodukte waehrend der gesamten Lagerzeit mit Sicherheit vermieden wird. Die Grenzwerte der spezifischen Aktivitaet in den Abfallprodukten zur Vermeidung eines zuendfaehigen Gas/Luft-Gemisches in der Kaverne betragen je nach Fuellungsgrad der Kaverne und Alter der fixierten Spaltpordukte 0,09 Ci/l bis 0,78 Ci/l. Die entsprechenden Grenzwerte der spezifischen Aktivitaet zur Vermeidung einer unzulaessigen Erwaermung der Abfaelle (> 700C) liegen je nach Alter der Spaltprodukte und Einlagerungsart zwischen 0,3 Ci/l und 0,7 Ci/l. (orig.)
Files
Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- KFK--2329
Conference
- Title
- Seminar on the bituminization of low and medium level radioactive wastes.
- Dates
- 18 May 1976.
- Place
- Antwerp, Belgium.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 8284391
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ASPHALTS; COMPUTER CALCULATIONS; DIAGRAMS; FEDERAL REPUBLIC OF GERMANY; HYDROGEN; INTEGRAL DOSES; RADIATION HEATING; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE STORAGE; RADIOACTIVE WASTES; RADIOLYSIS; SALT DEPOSITS
- Descriptors DEC
- BITUMENS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; DECOMPOSITION; ELEMENTS; EUROPE; GEOLOGIC DEPOSITS; HEATING; MANAGEMENT; NONMETALS; ORGANIC COMPOUNDS; OTHER ORGANIC COMPOUNDS; RADIATION DOSES; RADIATION EFFECTS; RADIOACTIVE MATERIALS; STORAGE; TAR; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE STORAGE; WASTES
Optional Information
- Notes
- 4 figs.; 2 tabs.; 10 refs.
- Secondary number(s)
- AED-Conf--76-433-002.