This report i> uunlf po»ihle by tiiuuuial support of the UHice of Nuclear Safety of the Department ol Energy as tlit' result ol a proposal by D. Yi. Smith nl thf Los Alamos National Laboratory. 1*1 n• iiunpilor> o| this version were assisted ahlv by an editorial advi.soi'N >;n>up I'onsisl inu, ol K. \\. .lohiison, .1. i. riioinas, and l)ixt)n Cailihan (all ol whoiu, wit 11 H. C. Paxton, ;-oiupilcd the original reporl). 1). R. Smith, K. 1). Clayton of Paciiic Northwest Laboratory and ('. M. lh>pper of Oak Hid^e Natiomil Laboratory. The in-dt|>th ell'tirt of [•' .. H. lolmsoii was es|)eciall\ valuable, We also wish to acknowledge the outstanding skill ol Ann Hopkins in preparation of this document. 11. C. Paxton N. L. I'mvost VI CRITICAL DIMENSIONS OF SYSTEMS CONTAINING-:tr r.-'-'I'll. AND-Xi V REVISION II. ('. I'axti.n and N. L. l'ruvost ABSTRACT This document is a revision of T1D-702K, CRITICAL DIMENSIONS OF SYSTEMS CONTAINING l'-:t \ Pii-'-1 ". AND 1 J:M (Kef. 1). I.NTRQDI'CTION This report is primarily a compilation o! critical data obtained from experiments performed in a number of laboratories during the period of 19-45 through 1985. It supplements the Nuclear Safety Guide Report TID-701H (Rev. 2)." in presenting critical data on which recommendations of the Guide are based. In some cases, calculated results are desirable to Hll in experimental data or to extend them. Where they appear in this report, they are identified as calculations because of the uncertainty associated with them. In general, the IB-group Hansen-Roach cross-section set 10 is used with the one-diinensional transport code, DSN," or its modern version, ONEDANT 12 in one dimension and TWODANT 1 " 1 in two dimensions. The reason for this choice is St rat ton's extensive comparison of results oi such calculations with experimental data. 14 Where this comparison is unfavorable, particularly for solution or hydrogeneous mixtures of few-percent " 15 l'-enriehed uranium, the Los Alamos MCNP Monte Carlo code 15 and cross-sections based on ENDF-B/Y* are used instead. This combination is also applied, in the few cases where finite-cylinder calculations are desired. Calculated extensions of experimental data are included to show the nature of trends, not to substitute for results of experiments. They should be used with caution. A fundamental aim of this document is 10 illustrate relationships among critical data. The compilation and correlation of data for this purpose, from many measurements in a number of laboratories, require a certain amount of normalization or reduction to common terms. Frequently, for example, the effects of variations in geometry or density must be removed to show trends in data. The manner in which these alterations may be made is discussed in the early section RELATIONS FOR CONVERSION TO STANDARD CONDITIONS. Reactor inockups and related critical assemblies are generally outside the scope of this document. Many of those that are appropriate to serve as computational models are fastueutron s\stems that are of secondary interest...

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