-
3
-
-
0038224818
-
-
ORNL/TM-12984, Oak Ridge National Laboratory
-
S. RAMAN, B. D. MURPHY, C. W. NESTOR, Jr., C. C. FOREMAN, W. S. FRASER, and T. D. NEWTON, "Dounreay PFR Irradiation History for the Joint US/UK Actinide Sample Exposure," ORNL/TM-12984, Oak Ridge National Laboratory (1995).
-
(1995)
Dounreay PFR Irradiation History for the Joint US/UK Actinide Sample Exposure
-
-
Raman, S.1
Murphy, B.D.2
Nestor C.W., Jr.3
Foreman, C.C.4
Fraser, W.S.5
Newton, T.D.6
-
4
-
-
20244374675
-
-
ORNL-6837, Oak Ridge National Laboratory
-
R. L. WALKER, J. L. BOTTS, R. J. HYDZIK, J. M. KELLER, J. K. DICKENS, and S. RAMAN, "Analytical Results of Physics Specimens and Dosimeters in Fuel Pins 1, 2, and 4, Irradiated in the Dounreay Prototype Fast Reactor," ORNL-6837, Oak Ridge National Laboratory (1994).
-
(1994)
Analytical Results of Physics Specimens and Dosimeters in Fuel Pins 1, 2, and 4, Irradiated in the Dounreay Prototype Fast Reactor
-
-
Walker, R.L.1
Botts, J.L.2
Hydzik, R.J.3
Keller, J.M.4
Dickens, J.K.5
Raman, S.6
-
5
-
-
0038563468
-
-
ORNL-5858, Oak Ridge National Laboratory
-
T. C. QUINBY, H. L. ADAIR, E. H. KOBISK, D. W. RAMEY, J. A. SETARO, J. L. BOTTS, J. H. COOPER, R. L. WALKER, J. E. BIGELOW, J. R. GIBSON, W. T. MARTIN, R. G. POPE, and S. RAMAN, "Preparation of Actinide Specimens for the US/UK Joint Experiment in the Dounreay Prototype Fast Reactor," ORNL-5858, Oak Ridge National Laboratory (1982).
-
(1982)
Preparation of Actinide Specimens for the US/UK Joint Experiment in the Dounreay Prototype Fast Reactor
-
-
Quinby, T.C.1
Adair, H.L.2
Kobisk, E.H.3
Ramey, D.W.4
Setaro, J.A.5
Botts, J.L.6
Cooper, J.H.7
Walker, R.L.8
Bigelow, J.E.9
Gibson, J.R.10
Martin, W.T.11
Pope, R.G.12
Raman, S.13
-
6
-
-
0038563469
-
-
ORNL-5986, Oak Ridge National Laboratory
-
R. L. WALKER, J. L. BOTTS, J. H. COOPER, H. L. ADAIR, J. E. BIGELOW, and S. RAMAN, "Characterization of Actinide Physics Specimens for the US/UK Joint Experiment in the Dounreay Prototype Fast Reactor," ORNL-5986, Oak Ridge National Laboratory (1983).
-
(1983)
Characterization of Actinide Physics Specimens for the US/UK Joint Experiment in the Dounreay Prototype Fast Reactor
-
-
Walker, R.L.1
Botts, J.L.2
Cooper, J.H.3
Adair, H.L.4
Bigelow, J.E.5
Raman, S.6
-
7
-
-
0037564941
-
Validation of minor actinide cross sections by studying samples irradiated for 492 days at the Dounreay Prototype Fast Reactor - II: Burnup calculations
-
K. TSUJIMOTO, N. KOHNO, N. SHINOHARA, T. SAKURAI, Y. NAKAHARA, T. MUKAIYAMA, and S. RAMAN, "Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor - II: Burnup Calculations," Nucl. Sci. Eng., 144, 2, 129 (2003).
-
(2003)
Nucl. Sci. Eng.
, vol.144
, Issue.2
, pp. 129
-
-
Tsujimoto, K.1
Kohno, N.2
Shinohara, N.3
Sakurai, T.4
Nakahara, Y.5
Mukaiyama, T.6
Raman, S.7
-
8
-
-
0024055469
-
Anion-exchange separation of nd and the transplutonium elements in spent nuclear fuels for burn-up determination
-
S. USUDA and N. KOHNO, "Anion-Exchange Separation of Nd and the Transplutonium Elements in Spent Nuclear Fuels for Burn-Up Determination," Sep. Sci. Technol., 23, 1119 (1988).
-
(1988)
Sep. Sci. Technol.
, vol.23
, pp. 1119
-
-
Usuda, S.1
Kohno, N.2
-
9
-
-
0024496243
-
Rapid preparation of high-resolution sources for alpha-ray spectrometry of actinides in spent fuel
-
N. SHINOHARA and N. KOHNO, "Rapid Preparation of High-Resolution Sources for Alpha-Ray Spectrometry of Actinides in Spent Fuel," Appl. Radiat. Isot., 40, 41 (1989).
-
(1989)
Appl. Radiat. Isot.
, vol.40
, pp. 41
-
-
Shinohara, N.1
Kohno, N.2
-
11
-
-
20244378053
-
Standard test method for atom percent fission in uranium plutonium fuel (neodymium-148 method)
-
E321-79, Vol. 12.02, American Society for Testing and Materials
-
"Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)," Annual Book of ASTM Standards, E321-79, Vol. 12.02, p.156, American Society for Testing and Materials (1985).
-
(1985)
Annual Book of ASTM Standards
, pp. 156
-
-
-
12
-
-
0001378131
-
ORIGEN2: A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials
-
A. G. CROFF, "ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials," Nucl. Technol., 62, 335 (1983).
-
(1983)
Nucl. Technol.
, vol.62
, pp. 335
-
-
Croff, A.G.1
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