1. |
An Experimental Study of the Molten Glass/Water Thermal Interaction Under Free and Forced Conditions |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 153-166
ArakeriV. H.,
CattonI.,
KastenbergW. E.,
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摘要:
AbstractMolten glass interacts explosively with water under certain contact mode conditions. The contact mode found explosive is as follows: Molten glass enters the water bath in the film boiling regime (as predicted by Dhir's correlation), and soon after entry the vapor film is perturbed sufficiently by an external pressure pulse. The ensuing reaction proceeds basically along the same lines as energetic tin/water interactions observed by several investigators. In the absence of this pressure pulse, the event is nonenergetic.The present findings are for a combination in which the hot material has a very low thermal diffusivity and the calculated interface temperature is significantly (∼180 K) below its melting temperature. This is similar to the characteristics of the UO2/sodium or UO2/water combinations. The observed explosive glass/water interactions show growth times on the order of a few milliseconds. The particulate size distribution from the present tests was coarser than the particulate size distribution from some in-pile and out-of-pile UO2/sodium interaction tests.
ISSN:0029-5639
DOI:10.13182/NSE78-A27197
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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2. |
Fissile Fuel Doubling Time Characteristics for Reactor Lifetime Fuel Logistics |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 167-187
HeindlerM.,
HarmsA. A.,
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摘要:
AbstractThe establishment of nuclear fuel requirements and their efficient utilization requires a detailed knowledge of some aspects of fuel dynamics and processing during the reactor lifetime. It is shown here that the use of the fuel stockpile inventory concept can serve effectively for this fuel management purpose. The temporal variation of the fissile fuel doubling time as well as non equilibrium core conditions are among the characteristics which thus become more evident. These characteristics—rather than a single figure-of-merit—clearly provide an improved description of the expansion capacity and/or fuel requirements of a nuclear reactor energy system.
ISSN:0029-5639
DOI:10.13182/NSE78-A27198
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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3. |
Cross Sections for the11B(α, p)14C Reaction in the Alpha-Particle Energy Range from 4.4 to 6.7 MeV |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 188-192
SouWen,
ShouChia,
WenMing,
HuaHsiao,
ChangJen,
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摘要:
AbstractFor the requirement of feasibility studies of the (11B +1H) controlled thermonuclear reactor system, the11B(α,p0)14C reaction has been studied with alpha particles of energies ranging from 4.4 to 6.7 MeV. Absolute differential cross sections were measured. Angular distributions and excitation functions are presented. The absolute error in the measured total cross sections is∼13%.
ISSN:0029-5639
DOI:10.13182/NSE78-A27199
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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4. |
Spectral Fine-Structure Effects in the Reactivity-Reaction-Rate Method for Determining Capture-to-Fission Ratios |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 193-204
GreenspanE.,
KarniY.,
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摘要:
AbstractEffects of fine-structure fluctuations in the importance function spectrum on the accuracy of the reactivity-reaction-rate (RRR) method for the determination of the effective capture-to-fission ratio () are investigated using a simple single-resonance model. It is found that multigroup calculations with flux-averaged group constants do not adequately take these effects into account. This can impair the accuracy of the value ofdetermined by the RRR method. A prescription for accurately taking the fine-structure spectral effects into account is given.
ISSN:0029-5639
DOI:10.13182/NSE78-A27200
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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5. |
Measurement of the Fission Cross Sections of Uranium-233 and Plutonium-239 Relative to Uranium-235 from 1 keV to 30 MeV |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 205-216
CarlsonG. W.,
BehrensJ. W.,
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摘要:
AbstractThe fission cross-section ratios of233U to235U and239Pu to235U were measured over the neutron energy range from 1 keV to 30 MeV at the Lawrence Livermore Laboratory 100-MeV Linac. Ionization fission chambers and the time-of-flight technique were used to take data simultaneously over the entire energy range. This provided accurate determinations of the shape versus neutron energy of the ratios. Two independent methods were used to determine the average value of each ratio in the interval from 1.75 to 4.0 MeV for the purpose of normalization. Over the 1-keV to 30-MeV range, the total uncertainties for the233U-to-235U data range from 2 to 4%; the239Pu-to-235U data uncertainties range from 1 to 4%.
ISSN:0029-5639
DOI:10.13182/NSE78-1
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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6. |
Neutron Capture Probabilities for Thick Samples at Resonance Energies |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 217-228
OhkuboMakio,
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摘要:
AbstractCapture and scattering probabilities for neutrons impinging on thick samples were measured by the Japan Atomic Energy Research Institute Linac time-of-flight spectrometer and were compared with those by Monte Carlo calculation. Sweeping the incident neutron energy, the capture probability shows peaks at resonance energies in the case of a thin sample, whereas it shows dips for a thick sample, i.e., saturation occurs just at resonance energies. This saturation phenomenon is analyzed by Monte Carlo calculation for a distribution of path lengths of incident neutrons in the sample until capture in the sample. The saturation values of capture probability at resonance energies Pcoare defined, and their dependence on the resonance parametersΓn/Γis examined. The relations between PcoandΓn/Γ, with parameters including recoil energy, are obtained by Monte Carlo calculation. The relations are verified by measurement of Pcofor many resonances of variousΓn/Γvalues. With the relation,Γn/Γcan be determined from Pco, which is not sensitive to sample thickness.
ISSN:0029-5639
DOI:10.13182/NSE78-A27202
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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7. |
The Importance Factor of a Source in Reactor Kinetics |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 229-234
LigouJ.,
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摘要:
AbstractThe expression for the source importance factor is derived in the frame of the adiabatic approximation. This factor plays an important role in the point kinetic equations when extraneous sources are present. It is shown how to get a very accurate value using standard codes that solve the steady-state transport (or diffusion) equation, but not the adjoint problem. Several numerical examples are discussed.
ISSN:0029-5639
DOI:10.13182/NSE78-A27203
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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8. |
Polynomial Approach to Reactor Kinetics Equations |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 235-242
YehKueng,
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摘要:
AbstractA method of solving reactor kinetics equations by using third-order Hermite polynomials for the approximation of neutron density (or power density) and delayed group precursors in finite time intervals is presented. When the reactivity is given, including the case of the feedback reactivity being a function of neutron density, this method can provide a straightforward procedure for computing reactor dynamics problems.
ISSN:0029-5639
DOI:10.13182/NSE78-A27204
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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9. |
Cross-Section Sensitivity Analysis of235U and238U Fission Rates Measured in a Graphite-Reflected Lithium Assembly |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 243-251
SekiYasushi,
MaekawaHiroshi,
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摘要:
AbstractIn a spherical lithium metal assembly with a graphite reflector, the changes in the fission rates of235U and238U due to changes in the cross-section sets of the constituent elements of the assembly are calculated. The results are discussed on the basis of experimental data. The fission rate of235U is found to be most sensitive to changes in the cross-section set of6Li in the lithium region, while in the graphite reflector, it is most sensitive to that of12C. The fission rate of238U is found to be more sensitive to changes in the cross-section sets of the elements in the stainless-steel structure rather than to those of lithium or graphite.
ISSN:0029-5639
DOI:10.13182/NSE78-A27205
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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10. |
Extension of the Width Fluctuation Correction to Reactions Involving Continuum Level Excitations |
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Nuclear Science and Engineering,
Volume 66,
Issue 2,
1978,
Page 251-254
ReffoG.,
FabbriF.,
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摘要:
AbstractThe concepts of decay-width-pooled distributions and of effective number of degrees of freedom have proven helpful in the calculation of inelastic scattering cross sections and emitted particle spectra, where channels leading to the excitation of bands of levels in the continuum are open at energies low enough for the width fluctuation effects to remain sizable.
ISSN:0029-5639
DOI:10.13182/NSE78-A27206
出版商:Taylor&Francis
年代:1978
数据来源: Taylor
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