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Critical loadings and precritical calculations for 2.9 inch pitch core in determining feasibility of isotopically enriched tungsten water moderated reactor for use as nuclear rocket
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The following topics are discussed: Boundary conditions for the SNS; The MUSTA experiment; Softening of the targe spectrum; Reflector size; Spectral tailoring; Spatial distribution; Time structure; Angular distribution; Target-mod...
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The following topics are discussed: Boundary conditions for the SNS; The MUSTA experiment; Softening of the targe spectrum; Reflector size; Spectral tailoring; Spatial distribution; Time structure; Angular distribution; Target-moderator configuration.
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The working group meeting was chaired by Watanabe. This working group was convened to set up an effort to characterize moderators at existing sources. The desired outcome was a formulation of the criteria, timing, and plans for th...
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The working group meeting was chaired by Watanabe. This working group was convened to set up an effort to characterize moderators at existing sources. The desired outcome was a formulation of the criteria, timing, and plans for the necessary
experiments. The results of the deliberations of this working group are summarized here. (auth)
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On 26-29 November 1984, the Agency convened at its Headquarters in Vienna the Technical Committee and Workshop on Advanced Light and Heavy Water Reactor Technology in order to provide an opportunity to review and discuss the curre...
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On 26-29 November 1984, the Agency convened at its Headquarters in Vienna the Technical Committee and Workshop on Advanced Light and Heavy Water Reactor Technology in order to provide an opportunity to review and discuss the current status and recent development in the layout and design of an advanced water reactor and to identify areas in which additional research and development are needed. The meeting was attended by 45 participants from 16 nations and 2 international organizations presenting 25 papers. The Conference presentations were divided into sessions devoted to the following topics: Advanced light water reactor programmes (6 papers); Advanced light water design, technology and physics (12 papers); Advanced heavy water reactors (7 papers). A separate abstract was prepared for each of these papers. (Atomindex citation 17:013246)
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The paper deals with methodological questions arising in connection with the measurement of neutron leakage from spherical assemblies simulating multiplication zones of controlled thermonuclear reactor blankets. A boron tank, whic...
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The paper deals with methodological questions arising in connection with the measurement of neutron leakage from spherical assemblies simulating multiplication zones of controlled thermonuclear reactor blankets. A boron tank, which has a number of advantages over other detectors of total absorption, served as the neutron detector. On the basis of the calculations performed, it was shown that surrounding the assembly under study with a layer of borated water serving as a neutron detector does not affect the processes of 14 MeV neutron multiplication. The boron tank has a constant recording efficiency for neutrons in the 0-6 MeV energy range. A procedure is proposed for measuring the leakage of neutrons from spherical samples with a central 14 MeV source. Translated from Russian. 8 references, 3 figures, 3 tables. (ERA citation 12:042780)
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A comparison was made between MCNP calculations and experimental measurements of the neutron spectrum from the liquid hydrogen moderator on ISIS. The calculations were performed for varying ortho/para concentrations, and demonstra...
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A comparison was made between MCNP calculations and experimental measurements of the neutron spectrum from the liquid hydrogen moderator on ISIS. The calculations were performed for varying ortho/para concentrations, and demonstrated a best fit for 100% para-hydrogen. The agreement between the measured and calculated results was good below 2? (i.e. for energies above 20 meV) but significant deviations were seen for longer wavelengths. A second study used the MCNP code for a detailed comparison of the time distributions and neutron spectra from poisoned liquid hydrogen and liquid methane moderators. The results indicate that the replacement of a liquid methane moderator with liquid hydrogen, in order to eliminate radiation damage effects, is an option which can be seriously considered. (auth)
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