Decontamination and dismantlement of the building 594 waste ion exchange facility at Argonne National Laboratory-East project final report
Description
The Building 594 D and D Project was directed toward the following goals: Removal of any radioactive and hazardous materials associated with the Waste Ion Exchange Facility; Decontamination of the Waste Ion Exchange Facility to unrestricted use levels; Demolition of Building 594; and Documentation of all project activities affecting quality (i.e., waste packaging, instrument calibration, audit results, and personnel exposure) These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the Waste Ion Exchange Facility and to allow, upon completion of the project, unescorted and unmonitored access to the area. The ion exchange system and the resin contained in the system were the primary areas of concern, while the condition of the building which housed the system was of secondary concern. ANL-E health physics technicians characterized the Building 594 Waste Ion Exchange Facility in September 1996. The characterization identified a total of three radionuclides present in the Waste Ion Exchange Facility with a total activity of less than 5 microCi (175 kBq). The radionuclides of concern were Co60, Cs137, and Am241. The highest dose rates observed during the project were associated with the resin in the exchange vessels. DOE Order 5480.2A establishes the maximum whole body exposure for occupational workers at 5 rem (50 mSv)/yr; the administrative limit at ANL-E is 1 rem/yr (10 mSv/yr)
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00012329; PURL: https://www.osti.gov/servlets/purl/12329-xRtlo8/webviewable/
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 37 p.
- Report number
- ANL/D-D--98-3
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 32064928
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- ACTIVITY LEVELS; AMERICIUM 241; CESIUM 137; COBALT 60; DECONTAMINATION; DEMOLITION; DOSE RATES; HAZARDOUS MATERIALS; ION EXCHANGE; OCCUPATIONAL SAFETY; RADIATION PROTECTION; RADIOACTIVE WASTE FACILITIES; SAFETY; SITE CHARACTERIZATION
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CLEANING; COBALT ISOTOPES; HEAVY NUCLEI; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; RADIOISOTOPES; SAFETY; SPONTANEOUS FISSION RADIOISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- W-31109-ENG-38
- Funding organization
- US Department of Energy (United States)