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Title: Preliminary calculations of release rates from spent fuel in a tuff repository. [Yucca Mountain Project]

Conference ·
OSTI ID:6049172
 [1]; ; ; ;  [2]; ;  [3]
  1. Pacific Northwest Lab., Richland, WA (USA)
  2. Lawrence Livermore National Lab., CA (USA)
  3. California Univ., Berkeley, CA (USA). Dept. of Nuclear Engineering Lawrence Berkeley Lab., CA (USA)

Time-dependent release rates of Tc-99, I-129, Cs-135, and Np-237 have been calculated for wet-drip and moist-continuous release modes from the engineered barrier system of a potential nuclear waste repository in unsaturated tuff, representative of a possible repository at Yucca Mountain in southern Nevada. We describe the modes of water contact and of release of dissolved radionuclides to the surrounding intact rock, and the corresponding calculational models. We list the parameter values adopted, and then present numerical results, conclusions, and recommendations. 21 refs., 5 figs., 2 tabs.

Research Organization:
Lawrence Livermore National Lab., CA (USA)
Sponsoring Organization:
DOE/RW
DOE Contract Number:
W-7405-ENG-48; AC06-76RL01830; AC03-76SF00098
OSTI ID:
6049172
Report Number(s):
UCRL-JC-104832; CONF-910435-43; ON: DE91007127; TRN: 91-004796
Resource Relation:
Conference: American Nuclear Society (ANS) international high level radioactive waste management conference, Las Vegas, NV (USA), 28 Apr - 3 May 1991
Country of Publication:
United States
Language:
English