Analysis of the characteristics of 238U, 232Th, 237Np, and 231Pa radiators for fission ionization chambers for measuring the neutron flux density in the ITER diverter-Reference-Cited by-同舟云学术

Analysis of the characteristics of 238U, 232Th, 237Np, and 231Pa radiators for fission ionization chambers for measuring the neutron flux density in the ITER diverter

Published:2009-01 Issue:1 Volume:106 Page:50-59
ISSN:1063-4258
Container-title:Atomic Energy
language:en
Short-container-title:At Energy

Author:

Egorov O. G.,Frunze V. V.,Kashchuk Yu. A.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1007/s10512-009-9130-5.pdf

Reference15 articles.

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2. W. Loosemore, R. Henderson, and G. Knill, “The continuous measurement of high–intensity thermal–neutron flux and gamma flux at high temperature,” Neutron Dos., 1, 89–101 (1963).

3. A. S. Krivokhatskii and Yu. F. Romanov, Production of Transuranium and Actinide Elements with Neutron Irradiation, Atomizdat, Mosow (1970).

4. O. I. Shetinin, A. B. Dmitriev, and E. K. Malyshev, “Radiators for fission chambers based on three-component mixtures of isotopes,” At. Énerg., 28, No. 2, 164–165 (1970).

5. E. K. Malyshev, “Current fission ionization chamber with nonconsumable radiator,” Prib. Tekh. Eksp., No. 5, 61–63 (1968).

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