The report was mostly generated through a review of abstracts of work completed to the point of being subjected to some form of publication in the open literature, formal ORNL reports, ORNL technical.memoranda, progress reports, or presentation at technical conferences. As much as possible we have reproduced the complete abstract of the original publication with only minor editing. In a few cases •progress reports were written specifically for this publication. The editors have selected the materials to be included in this report on the basis of perceived interests of DOE Nuclear Data Committee members and cannot claim completeness.

The report was mostly generated through a review of abstracts of work completed to the point of being subjected to some form of publication in the open literature, formal ORNL reports, ORNL technical memoranda, progress reports, or being presented at technical conferences. As much as possible we have reproduced the complete abstract of the original publication with only minor editing. In a few cases progress reports were written specifically for this publication. The authors have selected the materials to be included in this report on the basis of perceived interests of ERDA-NDC members and cannot claim completeness. OAK RIDGE NATIONAL LABORATORY A. CROSS SECTION MEASUREMENTS 1. Gamma-Ray Production Data During the reporting period the following gamma-ray production data obtained at ORELA were released: a. Production of Low Energy Gamma Rays by Neutron Interactions with Fluorine for Incident Neutron Ener ies Between 0.

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The reports in this document were submitted to the Energy Research and Development Administration Nuclear D?ta Committee (ERDA-NDC) in March 1977. The reporting laboratories are those having a substantial effort in measuring neutron and miclear cross sections of relevance to the U.S.^applied nuclear energy progiram. The material contained in these reports iis to be regarded as comprised of informal statements of recent developments i and preliminary data.s Persons wishing to make use of these data should contact the individual experimenter for further details. The data which appear in this document should be quoted only by permission of the contributor and should be referenced as private communication, and not by this document number. Appropriate subjects are listed as follows: ELEMENT QUANTITY TY"E ENERGY DOCUMENTATION LAB COMMENTS-I .-s A "-"l N MAX REF VOL P*GE OATt H B01 OIFF ELMTlC EXPT.PHOG 27*7 EROApNOC-9 2»» 477 HAR FOHLEH*FpRHARQ SCT.NOG, H tax AP-SOHPTION EXPT.PHOG MDG ERDAPNOC-9 27477 ANC SMJTH*PfltV VAL REVISED,WEIGHTED FIT.

The report was mostly generated through a review of abstracts of work completed to the point of being subjected to some form of publication in the open literature, formal ORNL reports, ORNL technical memoranda, progress reports, or presentation at technical conferences. As much as possible we have reproduced the complete abstract of the original publication with only minor editing. In a few cases progress reports were written specifically •for this publication. The editors have selected the materials to be included in this report on the basis of perceived interests of DOE Nuclear Data Committee members and cannot claim completeness. A. CROSS SECTION MEASUREMENTS 1. Gamma-Ray Production Data a. The Na(n,xy} Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV* (D. C. Larson and G. L. Morgan) Differential cross sections for the neutron-induced gammaray production from sodium have been measured for incident neutron energies between 0.2 and 20.0 MeV. The Oak Ridge Electron Linear Acceleratrir (ORELA) was used to provide the neutrons and a Nai spectrometer to detect the gamma rays at 125°. The data presented are the double differential cross section, d 2 cr/d~dE, for gamma-ray energies between 0.35 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 350 keV with higher resolution in the neutron energy is also presented. Finally, the excitation function for the 440-keV gamma ray is given for incident neutron energies between 400 keV and 20 MeV. The experimental results are compared with the Evaluated Nuclear Data Files (ENDF). b. Absolute Measurement of Cross Section** D. K. McConnell) 0.478-MeV and J. W. Measurements were performed using a Ge(Li) detector at 125° to a neutron beam whose energy ranged from 0.5 to 5.0 MeV. The neutron flux was measured using a proton recoil detector based on polyethylene foils and a silicon surface barrier detector.• The cross sections are accurate to a relative error of about •6% and an absolute uncertainty of about 8%. This isotropic gamma.-ray has potential as a secondary standard for inelastic scattering (n,n•y) cross sections.