100 research outputs found
Natural Nuclear Reactor Oklo and Variation of Fundamental Constants Part 1: Computation of Neutronics of Fresh Core
Using modern methods of reactor physics we have performed full-scale
calculations of the natural reactor Oklo. For reliability we have used recent
version of two Monte Carlo codes: Russian code MCU REA and world wide known
code MCNP (USA). Both codes produce similar results. We have constructed a
computer model of the reactor Oklo zone RZ2 which takes into account all
details of design and composition. The calculations were performed for three
fresh cores with different uranium contents. Multiplication factors,
reactivities and neutron fluxes were calculated. We have estimated also the
temperature and void effects for the fresh core. As would be expected, we have
found for the fresh core a significant difference between reactor and Maxwell
spectra, which was used before for averaging cross sections in the Oklo
reactor. The averaged cross section of Sm-149 and its dependence on the shift
of resonance position (due to variation of fundamental constants) are
significantly different from previous results.
Contrary to results of some previous papers we find no evidence for the
change of the fine structure constant in the past and obtain new, most accurate
limits on its variation with time:
-4 10^{-17}year^{-1} < d alpha/dt/alpha < 3 10^{-17} year^{-1}
A further improvement in the accuracy of the limits can be achieved by taking
account of the core burnup. These calculations are in progress.Comment: 25 pages, 14 figures, 12 tables, minor corrections, typos correcte
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Evaluation of verification methods for input-accountability measurements
As part of TASTEX related programs two independent methods have been evaluated for the purpose of providing verification of the amount of Pu charged to the head-end of a nuclear fuel processing plant. The first is the Pu/U (gravimetric method), TASTEX Task-L, and the second is the Tracer Method, designated Task-M. Summaries of the basic technology, results of various studies under actual plant conditions, future requirements, are given for each of the Tasks
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Burnup Determination of Nuclear Fuels. Project Report for the Quarter, January 1-March 31, 1965
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