1. |
Zeta Potentials of ThO2and of Stainless Steel as Related to Aggregation and Caking |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 143-149
LevyB.,
FritschA. R.,
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摘要:
AbstractThe streaming potential technique has been used to obtain the zeta potentials of ThO2in HCl, HI, HNO3, and H2SO4of various concentrations. The data are correlated with observed settling rates and tendency toward ThO2colloid formation. Streaming current measurements were made on type 304 stainless steel samples. Evidence is presented to demonstrate the significance of the zeta potentials of the ThO2and the stainless steel in the formation of thin films and thick cakes of ThO2on the stainless steel.
ISSN:0029-5639
DOI:10.13182/NSE59-A25572
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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2. |
Evaluation of a Bank of Slab-type Control Rods |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 150-155
DeutschRobert W.,
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摘要:
AbstractA method for evaluating a bank of slab-type control rods in enriched hydrogenous reactors considering both thermal and epithermal capture has been developed within the framework of three neutron energy groups. An absorption area technique that combines diffusion theory in the fuel moderator region and a transport condition at the control rod boundary is utilized. The effect of the absorption area is to decrease the source strength for the thermal and epithermal energy groups. The epithermal transmission probability for a non-1/υabsorber is found by an experimental reactivity comparison to a 1/υabsorber. Assuming that the absorption area is uniformly distributed throughout the core, a hand calculation can be made which determines the number, size, and composition of rods necessary to achieve a specific cold shutdown margin.
ISSN:0029-5639
DOI:10.13182/NSE59-A25573
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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3. |
Calculated Activities and Abundances of U235Fission Products |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 156-185
BollesR. C.,
BallouN. E.,
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摘要:
AbstractComputed disintegration rates and numbers of atoms (abundances) of each fission product radionuclide at various times after simultaneous slow neutron fission of 10,000 atoms of U235are presented. These results are based on fission yields from two different theories of independent fission yields. The computations treat both known and unknown fission product radionuclides. Half-lives and yields of the latter were estimated. The disintegration rate, number of active and inactive atoms, total number of atoms, and the percentage contribution to total activity and to the total number of atoms are presented for each element and for each chemical group of elements. The disintegration rate of the total fission product mixture according to each independent yield theory is also presented.
ISSN:0029-5639
DOI:10.13182/NSE59-A25574
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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4. |
Time Constant of Cylindrical Fuel Pin with Axial Coolant Flow1 |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 186-189
SandmeierH. A.,
O’SheaD. M.,
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摘要:
AbstractFrom the time dependent heat conduction and temperature distribution, an expression is derived for the time constant in a cylindrical fuel pin and cladding with axial coolant flow. The power production and the inlet temperature are functions of time. In the radial direction perfect mixing of the coolant is assumed. The average coolant temperature in a region is the average between inlet and outlet temperature assuming a linear rise in the axial direction. The set of partial differential equations can be solved by means of Laplace transform. The reciprocal of the roots of the characteristic equation for the temperature in the transform domain represents the time constants. The smallest root represents the dominant transient time constant. This dominant time constant is compared with a qualitative expression for the thermal relaxation time of a reactor after a power change given by Bethe. The numerical example used is a fuel pin in EBR-I Mark III in flowing NaK coolant at a core power generation of 1 Mw at various coolant flow conditions.
ISSN:0029-5639
DOI:10.13182/NSE59-A25575
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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5. |
Restricted Minimum Critical Mass |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 190-194
DevooghtJ.,
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摘要:
AbstractA continuously varying distribution of fissile material being difficult to realize in a minimum critical mass reactor, restricted distributions varying by steps are investigated in the particular case of“spherical”symmetry. It is shown that the crossing points of the restricted distribution with the unrestricted one are asymptotically distributed like the zeros of the orthogonal polynomials associated with the unrestricted distribution, as weight function. The differences between the minimum masses in the restricted and unrestricted cases are decreasing faster than 4−p, wherepstands for the number of steps of different heights. Other asymptotic properties are examined.
ISSN:0029-5639
DOI:10.13182/NSE59-A25576
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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6. |
A Note on the Elastic Constants of Uranium1 |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 195-196
RothmanS. J.,
FisherE. S.,
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摘要:
AbstractThe elastic moduli of polycrystalline uranium are calculated from the single crystal data, and are compared with the measured values. The discrepancies between data measured at different laboratories are also discussed.
ISSN:0029-5639
DOI:10.13182/NSE59-A25577
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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7. |
Elastic Constants of Polycrystalline Uranium1 |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 197-199
LaquerHenry L.,
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ISSN:0029-5639
DOI:10.13182/NSE59-A25578
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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8. |
Attenuation of 14-Mev Neutrons in Water and in 6-In. Lead and Water |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 199-200
DuggalV. P.,
PuriS. M.,
RamK. Sri,
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ISSN:0029-5639
DOI:10.13182/NSE59-A25579
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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9. |
The Inertia Transient in Reactor Draining |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 200-202
BurgreenDavid,
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ISSN:0029-5639
DOI:10.13182/NSE59-A25580
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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10. |
Plastic Bending of Rods or Tubes with Radial Temperature Distributions |
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Nuclear Science and Engineering,
Volume 5,
Issue 3,
1959,
Page 202-203
MerckxK. R.,
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ISSN:0029-5639
DOI:10.13182/NSE59-A25581
出版商:Taylor&Francis
年代:1959
数据来源: Taylor
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