Three Mile Island nuclear reactor accident of March 1979. Environmental radiation data: Volume IV. A report to the President's Commission on the Accident at Three Mile Island
Description
This report contains a listing of environmental radiation monitoring data collected in the vicinity of Three Mile Island (TMI) following the March 28, 1979 accident. These data were collected by the EPA, NRC, DOE, HHS, the Commonwealth of Pennsylvania, or the Bethlehem Steel Corporation. The original report was printed in September 1979 and the update was released in December 1979. This volume consists of the following: Table 10 Summary of US Department of Energy (DOE) sampling and analytical procedures; Table 11 Computer printout of environmental data collected by DOE; Table 12 Summary of Commonwealth of Pennsylvania sampling and analytical procedures; Table 13 Computer printout of environmental data collected by the Commonwealth of Pennsylvania; Table 14 Summary of State of New Jersey sampling and analytical procedures; Table 15 Computer printout of data collected by the State of New Jersey
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A17/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 385 p.
- Report number
- PB--81-175408
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13671587
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPILED DATA; ENVIRONMENTAL IMPACTS; NEW JERSEY; PENNSYLVANIA; RADIATION HAZARDS; RADIATION MONITORING; RADIOACTIVITY; REACTOR ACCIDENTS; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; DATA; ENRICHED URANIUM REACTORS; HAZARDS; HEALTH HAZARDS; INFORMATION; MONITORING; NORTH AMERICA; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; USA; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EPA--600/4-81-013E.