Results from NNWSI [Nevada Nuclear Waste Storage Investigations] Series 2 bare fuel dissolution tests [electronic resource]
The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Two bare spent fuel specimens plus the empty cladding hulls were tested in NNWSI J-13 well water in unsealed fused silica vessels under...
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Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Richland, Wash. : Oak Ridge, Tenn. :
Pacific Northwest National Laboratory (U.S.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1990.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Results from NNWSI [Nevada Nuclear Waste Storage Investigations] Series 2 bare fuel dissolution tests |h [electronic resource] |
| 260 | |a Richland, Wash. : |b Pacific Northwest National Laboratory (U.S.) ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1990. | ||
| 300 | |a 105 p. : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
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| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 09/01/1990. | ||
| 500 | |a "pnl--7169" | ||
| 500 | |a "DE91001051" | ||
| 500 | |a Wilson, C.N. | ||
| 520 | 3 | |a The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Two bare spent fuel specimens plus the empty cladding hulls were tested in NNWSI J-13 well water in unsealed fused silica vessels under ambient hot cell air conditions (25°C) in the currently reported tests. One of the specimens was prepared from a rod irradiated in the H. B. Robinson Unit 2 reactor and the other from a rod irradiated in the Turkey Point Unit 3 reactor. Results indicate that most radionuclides of interest fall into three groups for release modeling. The first group principally includes the actinides (U, Np, Pu, Am, and Cm), all of which reached solubility-limited concentrations that were orders of magnitude below those necessary to meet the NRC 10 CFR 60.113 release limits for any realistic water flux predicted for the Yucca Mountain repository site. The second group is nuclides of soluble elements such as Cs, Tc, and I, for which release rates do not appear to be solubility-limited and may depend on the dissolution rate of fuel. In later test cycles, ¹³⁷Cs, ⁹°Sr, ⁹⁹Tc, and ¹²⁹I were continuously released at rates between about 5 × 10⁻⁵ and 1 × 10⁻⁴ of inventory per year. The third group is radionuclides that may be transported in the vapor phase, of which ¹⁴C is of primary concern. Detailed test results are presented and discussed. 17 refs., 15 figs., 21 tabs. | |
| 536 | |b AC06-76RL01830. | ||
| 650 | 7 | |a Actinides. |2 local. | |
| 650 | 7 | |a Silicon Oxides. |2 local. | |
| 650 | 7 | |a Iodine 129. |2 local. | |
| 650 | 7 | |a Cladding. |2 local. | |
| 650 | 7 | |a Spent Fuels. |2 local. | |
| 650 | 7 | |a Cesium 137. |2 local. | |
| 650 | 7 | |a Ground Water. |2 local. | |
| 650 | 7 | |a Carbon 14. |2 local. | |
| 650 | 7 | |a Radioactive Waste Disposal. |2 local. | |
| 650 | 7 | |a Testing. |2 local. | |
| 650 | 7 | |a Dissolution. |2 local. | |
| 650 | 7 | |a Yucca Mountain Project. |2 local. | |
| 650 | 7 | |a Vapors. |2 local. | |
| 650 | 7 | |a Strontium 90. |2 local. | |
| 650 | 7 | |a Turkey Point-3 Reactor. |2 local. | |
| 650 | 7 | |a Robinson-2 Reactor. |2 local. | |
| 650 | 7 | |a Technetium 99. |2 local. | |
| 650 | 7 | |a Radionuclide Migration. |2 local. | |
| 650 | 7 | |a Yucca Mountain. |2 local. | |
| 650 | 7 | |a Environmental Sciences. |2 edbsc. | |
| 650 | 7 | |a Nuclear Fuels. |2 edbsc. | |
| 710 | 2 | |a Pacific Northwest Laboratory. |4 res. | |
| 710 | 2 | |a Pacific Northwest National Laboratory (U.S.). |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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