DESTRUCTIVE AND NONDESTRUCTIVE BURNUP DATA FROM NATURAL UO₂ FUEL. [electronic resource]
Uranium Isotopes/determination In Spent Uranium Oxide (uo$sub 2$) By Mass Spectrometry; Cesium Isotopes Cs-137/determination As Measure Of Fission Product Concentration In Spent Uranium Oxide (uo$sub 2$) By Counting; Uranium/determination In Spent Uranium Oxide (uo$sub 2$) By Sample Weighing; Neodym...
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| Online Access: |
Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C : Oak Ridge, Tenn. :
United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1971.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a DESTRUCTIVE AND NONDESTRUCTIVE BURNUP DATA FROM NATURAL UO₂ FUEL. |h [electronic resource] |
| 260 | |a Washington, D.C : |b United States. Dept. of Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1971. | ||
| 300 | |a Pages: 156 : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 01/01/1971. | ||
| 500 | |a "bnwl--1568" | ||
| 500 | |a Christensen, D.E.; Matsen, R.P. | ||
| 520 | 0 | |a Uranium Isotopes/determination In Spent Uranium Oxide (uo$sub 2$) By Mass Spectrometry; Cesium Isotopes Cs-137/determination As Measure Of Fission Product Concentration In Spent Uranium Oxide (uo$sub 2$) By Counting; Uranium/determination In Spent Uranium Oxide (uo$sub 2$) By Sample Weighing; Neodymium Isotopes Nd-148/ Determination As Measure Of Fission Product Concentration In Spent Uranium Oxide (uo$sub 2$) By Isotope Dilution; Plutonium Isotopes/determination In Spent Uranium Oxide (uo$sub 2$) By Mass Spectrometry; Uranium Oxides Uo$sub 2$/analysis Of Spent, For Fission Products, Plutonium, And Uranium; Plutonium Recycle Test Reactor/ Fuels For, Burnup Data For Spent Natural Uranium Oxide (uo$sub 2$), (e); Plutonium/determination In Spent Uranium Oxide (uo$sub 2$) By $alpha$ Counting Or Isotope Dilution. | |
| 536 | |b AT(45-1)-1830. | ||
| 650 | 7 | |a Alpha Spectrometers-- Isotope Dilution-- Plutonium. |2 local. | |
| 650 | 7 | |a Fission Products-- Isotope Dilution-- Neodymium 148. |2 local. | |
| 650 | 7 | |a Quantitative Analysis. |2 local. | |
| 650 | 7 | |a Cesium 137-- Fission Products-- Gamma Spectrometers. |2 local. | |
| 650 | 7 | |a Burnup-- Fission Products-- Fuels-- Isotope Ratio-- Natural Uranium Fuel-- Plutonium Isotopes-- Prtr-- Spent Fuel Elements-- Tables-- Uranium Dioxide-- Uranium Isotopes. |2 local. | |
| 650 | 7 | |a Mass Spectrometers-- Plutonium Isotopes-- Uranium Isotopes. |2 local. | |
| 650 | 7 | |a Uranium Dioxide Gravimetry-- Uranium. |2 local. | |
| 710 | 2 | |a Pacific Northwest Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 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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