The prompt-neutron-induced-fIssion spectre of 233 U, 23! >U, 239 Pu and 2"tOp u are measured relative to the prompt-spontaneousfission-neutron spectrum of 252 Cf. The fission of 233 U, 235 U, and 23^P U is induced by ~550 keV neutrons and that of 21 *°Pu bỹ 850 keV neutrons. The emitted fission neutrons are observed over the energy range i 0.5-10.0 MeV using tirae-of-flight techniques. Analysis of the measured values indicates that the average-fission-neutron energies are-123±30(233 U),-157±24(235 U),-76±29(239 Pu) and-46±29(21 +0p u) keV relative to that of 2 "cf. The experimental results are compared with those of ENDF/B-V and a simple behavior of average-prompt-fission-neutron energies is suggested.

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The Nuclear Data and Measurements Series presents results of studies in the field of microscopic nuclear data. The primary objective is the dissemination of information in the comprehensive form required for nuclear technology applications. This Series is devoted to: a) measured microscopic nuclear parameters, b) experimental techniques and facilities employed in measurements, c) the analysis, correlation and interpretation of nuclear data, and d) the evaluation of nuclear data. Contributions to this Series are reviewed to assure technical competence and, unless otherwise stated, the contents can be formally referenced. This Series does not supplant formal journal publication but it does provide the more extensive information required for technological applications (e.g., tabulated numerical data) in a timely manner. Copies on microfiche can be obtained by contacting:

The Nuclear Data and Measurements Series presents results of studies in the field of microscopic nuclear-data. The primary objective is the dissemination of information in the comprehensive form required for nuclear technology applications. This Series-is devoted to: a) measured microscopic nuclear parair/iiters, b) experimental techniques and facilities employed in measure-•mentu, c) the analysis,) correlation and interpretation of nuclear data, and * d) the evaluation of nuclear data. Contributions to this Series are reviewed to assure technical competence and, unless otherwise stated, the contents can be formally referenced. This Series does not supplant formal journal publication but it does provide the more extensive information required for technological applications (e.g., tabulated numerical data) in a timely manner.