Nuclear data guide for reactor neutron metrology
This guide contains data for 87 reactions and 11 fission products. Table 1 surveys these reactions, together with the main gamma rays of the reaction products. Two tables of accurate gamma energies are incorporated for gamma spectrometer calibration. Table 4 gives the data calculated for the energy-dependent cross-sections of the DOSCROS84 library. A summary of these data and data calculated by another method is given in Table 5. Table 6 summarises experimental and calculated data for spectrum averaged cross-section in a 235U fission spectrum. The averaged cross-sections for the 252Cf spectrum are given in Table 7. Table 8 gives a summary of cross-sections at 14 MeV. Information on the availability of multigroup cross-section data is given in Table 9. Values of effective cross-section and accompanying threshold data, giving the smallest deviation from the energy-dependent cross-section, are presented in Tables 10 and 11. Appendix 1 gives air kerma rate constants. Appendices 2 and 3 display the various representations of the 235U fission spectrum and the 252Cf spectrum. Neutron irradiation damage is discussed in Appendix 4. Appendix 5 lists information on reference materials for neutron metrology.
Bibliographic Reference: EUR 12354 EN (1989) 1371 pp.
Availability: Kluwer Academic Publishers Group, P.O. Box 322, 3300 AH Dordrecht (NL)
ISBN: ISBN 0-7923-0486-1
Record Number: 199010536 / Last updated on: 1994-12-01
Original language: en
Available languages: en