1. |
Thermal Self-Shielding and Edge Effects in Absorbing Foils |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 259-262
CraneJ. L.,
DoernerR. C.,
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摘要:
Self-shielding and edge corrections were investigated for varying thicknesses of 1 cm dia. gold foils. Test foils were irradiated in the hohlraum or air chamber of the Cornell University TRIGA Mark II reactor. The self-shielding effect was determined from the activation of a series of foils of different thicknesses and the edge correction from the activities of successively smaller concentric rings punched from the parent foil. Edge effects were found in the 2.5 mil and thicker foils and were statistically significant only in the outer millimeter of the foil radius. After cutting off the outer millimeter of the foils, the activity was found to follow the law for infinite foils.
ISSN:0029-5639
DOI:10.13182/NSE63-A26528
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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2. |
Theory of Pulsed Neutron Source Measurements* |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 263-270
GarelisEdward,
RussellJohn L.,
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摘要:
A new method of utilizing pulsed neutron source measurements for the determination of the subcriticality of an assembly directly in terms of dollars is proposed. Essentially, the method determines the parameter (kβ/l) using the complete response curve of a repetitively pulsed assembly after the quasi-equilibrium state has been attained. This value of (kβ/l) coupled with the usualα-measurement, assuming the prompt decay constant to be dominant, yields the reactivity directly. The analytical model is based on a bare one-group diffusion theory system withm-delayed precursors. The application of these results to experiment shows that their applicability is much broader than the simple analytical model would indicate.
ISSN:0029-5639
DOI:10.13182/NSE63-A26529
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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3. |
Resonance Integral Calculations for U238Lattices* |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 271-279
LevineMelvin M.,
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摘要:
Resonance integrals computed by the method of Chernick and Vernon are compared with precise results from a series of Monte Carlo calculations with very large numbers of histories. The range of applicability of the method of Chernick and Vernon is exhibited by this comparison. Some simplifications are made in the method of presentation of the resonance integral results so that the correlation among single lumps and lattices of various compositions is improved.
ISSN:0029-5639
DOI:10.13182/NSE63-A26530
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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4. |
Coating Costs for Ceramic-Coated Nuclear-Fuel Particles |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 280-290
OxleyJ. H.,
BrowningM. F.,
BlockerJ. M.,
DrydenC. E.,
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ISSN:0029-5639
DOI:10.13182/NSE63-A26531
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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5. |
Superprompt-Critical Behavior of an Unmoderated, Unreflected Uranium—Molybdenum Alloy Reactor |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 291-298
MihalczoJohn T.,
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摘要:
The time-dependent behavior of the neutron population in an unreflected, unmoderated cylindrical assembly of 90 wt.% uranium (93.2 wt.% U235), 10 wt.% molybdenum alloy following a rapid establishment of superprompt critical conditions with negligible initial neutron population has been studied. Reactivity increases up to 11 cents above prompt critical resulted in bursts yielding as many as 1.8×1017fissions and peak power up to 100,000 Mw with periods as short as 16µsec and temperature increases as large as 400°C. For bursts greater than about 6×1016fissions the safety block—a piece of the core held in place by an electromagnet—is driven out by pressure waves about 225µsec after the peak of the burst.
ISSN:0029-5639
DOI:10.13182/NSE63-A26532
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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6. |
Effective Fission Cross Sections and Neutron Spectra in an NRX Type Uranium Metal Rod |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 299-314
BighamC. B.,
KushneriukS. A.,
TunnicliffeP. R.,
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摘要:
Fission cross section ratios of U233, U235, and Pu239and capture rates in Mn55and In115have been measured in an NRX type uranium metal rod irradiated in a heavy water moderated reactor. The results have been compared to the values obtained using a model designed for NRX burnup calculations. Agreement was obtained using an“incurrent”spectrum composed of a Maxwellian thermal component and an epithermal component of the form obtained from neutron spectrometer measurements. Changes in spectrum caused by the light water coolant were also studied.
ISSN:0029-5639
DOI:10.13182/NSE63-A26533
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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7. |
Fission Fragment Distribution in Irradiated UO2 |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 315-328
BermanR. M.,
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摘要:
Four irradiated UO2samples were ground to break them along grain boundaries, then dissolved in a series of successive leaches with 3NHNO3. The successive acid extractions were then analyzed for Cs138, Ce144, Zr95, Sr90, and Eu155, as well as total uranium. Very considerable variation in the specific activities of the fission fragments was found between one acid extraction and another of the same sample. The fission products were concentrated in the first and last portions of the material to dissolve. In one sample, which underwent irradiation for a very short time, the increase in concentration in the last portion to dissolve was not observed. It is speculated, on this and other evidence, that fission fragments do not remain in solid solution in uranium dioxide, but instead migrate to grain boundaries and other lattice defect sites.
ISSN:0029-5639
DOI:10.13182/NSE63-A26534
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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8. |
Approximate Escape Probabilities |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 329-335
SauerA.,
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摘要:
The rational approximation to the escape probability is generalized to contain a geometry dependent parameter. In this way, approximate expressions that are both simple and remarkably accurate are obtained for the escape probability from solid and hollow fuel rods, and for the Dancoff correction in regular rod lattices. These approximations are derived from suitably chosen one-parametric chord distribution functions that have the same general character as the exact chord distributions of the fuel and moderator regions. It is shown that it is reasonable to determine the parameter belonging to each geometry—the geometric index—from the condition that the logarithmic moment of the exact and the approximate chord distribution functions be equal. The geometric indices are given for solid and hollow fuel rods, and for square and hexagonal lattice configurations. For solid or hollow fuel rods the error in the approximation is less than 1 %. The Dancoff correction for rod lattices is obtained with comparable accuracy.
ISSN:0029-5639
DOI:10.13182/NSE16-03-329
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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9. |
Xenon Oscillations in Finite Reactors |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 336-337
PearceR. M.,
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ISSN:0029-5639
DOI:10.13182/NSE63-A26536
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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10. |
Resonance Absorption in Materials with Grain Structure (Addendum) |
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Nuclear Science and Engineering,
Volume 16,
Issue 3,
1963,
Page 337-338
NordheimL. W.,
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ISSN:0029-5639
DOI:10.13182/NSE63-A26538
出版商:Taylor&Francis
年代:1963
数据来源: Taylor
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