scholarly journals Radiation doses in granite around emplacement holes in the Spent Fuel Test - Climax. Final report

10.2172/59328 ◽  
1984 ◽  
Author(s):  
R.A. Van Konynenburg
Keyword(s):  
Final Report ◽  
Radiation Doses ◽  
Spent Fuel

The Effect of Bromide on Oxygen Yields in Homogeneous α-radiolysis

MRS Advances ◽  
2017 ◽  
Vol 2 (13) ◽  
pp. 711-716 ◽  
Author(s):  
Lovisa Bauhn ◽  
Christian Ekberg ◽  
Patrik Fors ◽  
Kastriot Spahiu
Keyword(s):  
Radiation Field ◽  
Spent Nuclear Fuel ◽  
Radiation Doses ◽  
Deep Geological Repository ◽  
Spent Fuel ◽  
Mass Spectrometric Measurement ◽  
Α Decay ◽  
Geological Repository ◽  
Dissolved Ions ◽  
Dissolved Hydrogen

ABSTRACTIn a scenario where ground water enters a canister for spent nuclear fuel in a deep geological repository, the presence of dissolved ions in the water could possibly influence the fuel dissolution due to effects on radiolysis yields. One species of particular interest in this context is bromide, which has a proven ability to scavenge hydroxyl radicals much faster than molecular hydrogen does. As a result, bromide could inhibit the beneficial effect of dissolved hydrogen, which has been shown in γ-radiolysis experiments. However, already a few hundred years after repository closure, α-decay starts to dominate in the radiation field from the spent fuel. Hence, the effects of α-radiolysis are expected to govern the fuel dissolution over the geological timeframes of the repository. In the present work, α-radiolysis experiments have been performed to determine the effect of bromide ions on the yield of hydrogen peroxide by mass spectrometric measurement of its decomposition product oxygen. The use of high activity 238Pu solutions has made it possible to study this effect during pure α-radiolysis from a homogeneously distributed radiation field. To simulate deep bedrock repository conditions, and to minimize the influence of in-leaking O2 from air, the studies were performed using graphite sealed stainless steel autoclaves with an initial atmosphere of 10 bar H2. The results show that addition of 1 mM Br- to the solution gives no significant effect on the O2 yield for radiation doses up to 2 MGy. This lack of effect is most likely explained by the limited radical escape yields from radiation tracks in pure α-radiolysis.

scholarly journals Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report.

2008 ◽  
Author(s):  
Michael Warren Gregson ◽  
John E. Brockmann ◽  
Olivier Loiseau ◽  
Lindsay A. Klennert ◽  
Oliver Nolte ◽  
...  
Keyword(s):  
Final Report ◽  
Spent Fuel ◽  
Test Program ◽  
Program Characterization

scholarly journals Development of Techniques for Spent Fuel Assay – Differential Dieaway Final Report

2016 ◽  
Author(s):  
Martyn Thomas Swinhoe ◽  
Alison Goodsell ◽  
Kiril Dimitrov Ianakiev ◽  
Metodi Iliev ◽  
David J. Desimone ◽  
...  
Keyword(s):  
Final Report ◽  
Spent Fuel

Measures of Geologic Isolation

2004 ◽  
Vol 824 ◽  
Author(s):  
William M. Murphy
Keyword(s):  
Scientific Basis ◽  
Yucca Mountain ◽  
Radiation Doses ◽  
Spent Fuel ◽  
Carbon 14 ◽  
Decay Series ◽  
Regulatory Measures ◽  
Geologic Setting ◽  
High Level

AbstractIsolation in a geologic setting has been the generally favored solution to the high-level radioactive waste (HLW) problem since a scientific basis for nuclear waste management began to be formulated over half a century ago. Although general features of suitable settings have been enumerated, quantitative measures of the safety of geologic isolation of HLW are challenging to devise and to implement. Some regulatory measures of isolation for the proposed repository at Yucca Mountain, Nevada, have be devised and revised involving considerations of global releases, groundwater travel time, and time and space scales for isolation. In current Yucca Mountain specific regulations, the measure of long-term safety hinges on probabilistic estimates of radiation doses to the average member of a maximally exposed group of people living about 18 km down the groundwater flow gradient within 10,000 years after permanent closure of the repository. From another perspective, hydrogeochemical studies provide quantitative measures of system openness and the ability of geologic systems to isolate HLW. Hydrogeochemical data that bear on geologic isolation of HLW at Yucca Mountain include precipitation of radionuclides in stable mineralogical products of spent fuel alteration, ages of natural secondary mineralization in the mountain, uranium decay-series isotopic data for system openness, bomb-pulse isotope occurrences, and ambient carbon-14 distributions.

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