Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

[K reactor probabilistic risk assessment]. Final report

Technical Report ·
DOI:https://doi.org/10.2172/10118393· OSTI ID:10118393
 [1]
  1. Univ. of New Mexico, Albuquerque, NM (United States)
This report contains the original University of New Mexico inputs to various aspects of LANL`s Probabilistic Risk Assessment of K Reactor. Most of this input was ultimately incorporated into one of the two referenced reports. Since the work summarized in the attached sheets was preliminary in nature and later revised under Subcontract 9-X60-D1200-1, Task 46, the following reports should be consulted for more current technical information: J.L. Darby, D.V. Rao, B.E. Simpkins, and F.E. Haskin, Savannah River Site K Reactor Filter Heatup Model, SEA Report No. 90-500-007-A-1, July 31, 1991 and D.W. Stack et al, Electrical Systems` Contribution to K Reactor Accident Sequence Frequency, LANL Report LA-CP-01-415, February 1992.
Research Organization:
Los Alamos National Lab., NM (United States); New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
10118393
Report Number(s):
LA-SUB--93-222; ON: DE94005671
Country of Publication:
United States
Language:
English