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11. |
The Effective Cross Section for the16O(d, n)17F Reaction for Fission Neutrons Moderated by Heavy Water |
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Nuclear Science and Engineering,
Volume 50,
Issue 1,
1973,
Page 79-80
PruysH. S.,
GanapolB. D.,
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摘要:
AbstractThe effective cross section for the16O(d, n)17F reaction for fission neutrons moderated by D2O has been calculated, using the recoiling deuteron formalism of Hammar and Forsén. A value of∑n= 4.8×10-7cm-1is reported.
ISSN:0029-5639
DOI:10.13182/NSE73-A22592
出版商:Taylor&Francis
年代:1973
数据来源: Taylor
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12. |
Revised Delayed-Neutron Yield Data |
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Nuclear Science and Engineering,
Volume 50,
Issue 1,
1973,
Page 80-82
EvansA. E.,
ThorpeM. M.,
KrickM. S.,
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摘要:
AbstractValues of the yield of delayed neutrons from fission previously reported by Masters, Thorpe, and Smith and by Krick and Evans have been reevaluated following refinement of earlier measurements and calibrations. Except for238U, the values for fast fission are in agreement with earlier results of Keepin.
ISSN:0029-5639
DOI:10.13182/NSE73-A22593
出版商:Taylor&Francis
年代:1973
数据来源: Taylor
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13. |
Merit Index for Gas-Cooled Reactor Heat Transfer |
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Nuclear Science and Engineering,
Volume 50,
Issue 1,
1973,
Page 83-85
MeleseG.,
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摘要:
AbstractA simple merit index has been derived to compare potential improvements in gas-cooled nuclear reactor cores, such as artificial surface roughening of the fuel rods. For given pumping-to-thermal power ratio, the core output per unit heat transfer area is proportional to the merit index (N3/f)1/2. Stanton number, or dimensionless surface heat transfer coefficient, is Ns, and f is the friction factor.
ISSN:0029-5639
DOI:10.13182/NSE73-A22594
出版商:Taylor&Francis
年代:1973
数据来源: Taylor
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14. |
Thermal Characterization of Restructured Fuel |
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Nuclear Science and Engineering,
Volume 50,
Issue 1,
1973,
Page 85-87
FriedlandAaron J.,
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摘要:
AbstractThree-region restructured fuel, with given thermal characteristics, may be represented by an effective conductivity integral function Y(T). For any fuel surface temperature Tsand linear heat generation rate q, the maximum fuel temperature Tvis found from the relation Yv- Ys= q. Region radii and molten fuel fraction appear in the groups qR2/R2land qF as functions of Yv- Ye.
ISSN:0029-5639
DOI:10.13182/NSE73-A22595
出版商:Taylor&Francis
年代:1973
数据来源: Taylor
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15. |
A Program for Calculating Thermal Neutron Scattering Kernels |
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Nuclear Science and Engineering,
Volume 50,
Issue 1,
1973,
Page 88-88
GibbsA. G.,
LindenmeierC. W.,
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ISSN:0029-5639
DOI:10.13182/NSE73-A22596
出版商:Taylor&Francis
年代:1973
数据来源: Taylor
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16. |
Nuclear Radiation Physics |
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Nuclear Science and Engineering,
Volume 50,
Issue 1,
1973,
Page 89-89
UnderwoodNewton,
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PDF (116KB)
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ISSN:0029-5639
DOI:10.13182/NSE73-A22597
出版商:Taylor&Francis
年代:1973
数据来源: Taylor
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