Determination of <i>k</i><sub>∞</sub> from Critical Experiments with the PCTR

Donahue, D. J.; Lanning, D.D.; Bennett, R.A.; Heineman, R.E.

doi:10.13182/nse58-a25530

Cited by 19 publications

(3 citation statements)

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“…In this case the spectrum was appropriate to a steam-cooled fast breeder reactor. Their method is based on the technique pioneered by Donahue et a1 (1958) for the Physical Constants Testing Reactor (PCTR) at the Hanford Laboratories. This makes use of the fact that there would be no change in either the neutron density or its energy distribution in ~J-I infinite critical homogeneous medium if any volume of the medium were replaced by a vacuum.…”

Section: 42mentioning

confidence: 99%

The nuclear physics of fast reactors

Beynon¹

1974

Rep. Prog. Phys.

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T h e nuclear physics aspects of fast reactor research and development are reviewed with particular emphasis on the evolving experimental and theoretical techniques for predicting and understanding the performance of the liquid metal fast breeder reactor (LMFBR). A general account of this oxide-fuelled liquid-sodiumcooled system is given in the introductory section. This leads to a discussion of the physical aspects of the uranium-plutonium breeding cycle. Consideration is given to the sensitivity of the cycle to the competing processes of radiative capture and fission. Recent measurements of the capture-to-fission ratio a are given and methods of defining the breeding ratio of a system are examined. Recently used techniques for determining the prompt neutron fission yield Cp(E) and the prompt neutron energy spectrum x ( E ) are mentioned and the available techniques for measuring 42 5 60 15 62.5 20 200 66 40 20 60 12

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Section: 42mentioning

confidence: 99%

The nuclear physics of fast reactors

Beynon¹

1974

Rep. Prog. Phys.

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“…CURRENT In the THERMOS code, the basic neutron balance equation is written as as (2) , (1) where We will consider a one-dimensional system (slab, cylinder, or sphere) and denote the spatial coordinate by r.…”

Section: Bnwl-634mentioning

confidence: 99%

“…vised in Battelle-Revised-Thermos. The program consists of an overlay of the Fortran-IV codes HRG, (1,2) Battelle-Revised-Thermos, 3and HFN. 4The program also produces broad group cross sections from the HRG-Battelle-Revised-Thermos overlay portion for use in various diffusion and transport theory codes.…”

Section: Mixture Expansion Input Revisionsmentioning

confidence: 99%