Measurement of 233U Fission Spectrum-Averaged Cross Sections for Some Threshold Reactions
Measurement of 233U Fission Spectrum-Averaged Cross Sections for Some Threshold Reactions

Author: K. Kobayashi

Publisher:

Published: 1994

Total Pages: 7

ISBN-13:

DOWNLOAD EBOOK

The 233U fission spectrum-averaged cross sections for twelve threshold reactions were measured relative to the average cross section of 0.688±0.040 mb for the 27Al(n,?)24Na reaction. The reference value was obtained by calculation using the energy dependent cross section in the Japanese Evaluated Nuclear Data Library (JENDL) Dosimetry File and the Watt-type fission spectrum in ENDF/B-VI. General agreement was seen between the measured and the calculated fission-spectrum averaged cross sections. However, there exist discrepancies of more than 10 % between the measured and the calculated average cross sections for the 24Mg(n,p)24Na, 47Ti(n,p)47Sc, and 64Zn(n,p)64Cu reactions. The tendencies in the calculated-to-measured ratios are similar to those for 235U fission spectrum-averaged cross sections we previously measured.

Reactor Dosimetry
Reactor Dosimetry

Author: Harry Farrar

Publisher: ASTM International

Published: 1994

Total Pages: 854

ISBN-13: 0803118996

DOWNLOAD EBOOK

Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa

The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy
The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy

Author:

Publisher:

Published: 1986

Total Pages:

ISBN-13:

DOWNLOAD EBOOK

The measurement of the fission cross section ratios of nine isotopes relative to 235U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for 235U are: 23°Th - 0.290 +- 1.9%; 232Th - 0.191 +- 1.9%; 233U - 1.132 +- 0.7%; 234U - 0.998 +- 1.0%; 236U - 0.791 +- 1.1%; 238U - 0.587 +- 1.1%; 237Np - 1.060 +- 1.4%; 239Pu - 1.152 +- 1.1%; 242Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.

Cross Section Measurement for the 52Cr(n, P)52V Reaction Near Threshold
Cross Section Measurement for the 52Cr(n, P)52V Reaction Near Threshold

Author:

Publisher:

Published: 1979

Total Pages:

ISBN-13:

DOWNLOAD EBOOK

Cross sections for this reaction were determined in the range 5.3 to 9 MeV using a previously-reported pulsed-accelerator technique to measure gamma ray activity from 3.75 m 52V. Very few experimental data have been reported for this reaction, and little was known about the threshold region prior to the present experiment. The results of this work (in conjunction with other available cross section information) were used in the computation of fission-spectrum averages which are of interest for reactor applications.

Remarks Concerning the Accurate Measurement of Differential Cross Sections for Threshold Reactions Used in Fast-neutron Dosimetry for Fission Reactors
Remarks Concerning the Accurate Measurement of Differential Cross Sections for Threshold Reactions Used in Fast-neutron Dosimetry for Fission Reactors

Author:

Publisher:

Published: 1976

Total Pages:

ISBN-13:

DOWNLOAD EBOOK

Some remarks are submitted concerning the measurement of differential cross sections for threshold reactions which are used in fast-neutron dosimetry for fission reactors. The objective is to familiarize the reader with some of the problems associated with these measurements and, in the process, to explain why the existence of large discrepancies in the data sets for many of these reactions is not surprising. Limits to the accuracy which can be expected for these cross sections in the near future--using current technology and available resources--are examined in a general way and recommendations for improving the accuracy of the differential data base for dosimetry reactions are presented.