Review of Molten Salt Reactor Physics Calculations [Disc 2]

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LEGAL NOTICE This report was prepared as an account of Government sponsored work. nor the Commission, nor any person acting an boholf of the Commission: Neither the United States, A. Makes any warranty or reprmsentatian, expressed or implied, with respect to the accuracy, completaness, or usefulmss of tho information contained in this rapart, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or B. Assumes any liabilities with respect to the use of, or for damages resulting from the use of any information, apparatus, method, of process disclosed in this report. As used in the above, "person acting on behalf of the Commission" includes any employee or contractor of the Commission, or employee of such contractor, to the extent that such employee or contractor of the Commission, or employee of svch contractor prepares, disseminates, or provides accesa to, any Information pursuant to his omplayment of contract with the Commission, or his employment with such contractor.
3 . CONTENTS Intmduction ................................................... Summary of Results and Recommendations .......................... Cross Sections .................................................. Fission Product Treatment ....................................... Cell Calculations ............................................... Two-Dimensional Calculations .................................... Depletion Calculations .......................................... Page 5 8 14 25 34 44 52
Page 1: OAK RIDGE NATIONAL LABORATORY opero
Page 6 and 7: 6 The cross sections selected were
Page 8 and 9: 8 2. QF RESULTS AND FECOMMEIPDATION
Page 10 and 11: 10 2. The average '1 of 235U was 1.
Page 12 and 13: The power distributions obtained in
Page 14 and 15: 14 3. ao6S SECTIONS For the most pa
Page 16 and 17: Table 3.1 (cont 'a) mUclide ua(2200
Page 18 and 19: I Table 3.1 (eont'd) Nuclide Ua(220
Page 20 and 21: Table 3.2 20 (cont'd) W i Absorptio
Page 22 and 23: 22 on an average fuel salt temperat
Page 24 and 25: 24 28. 29 9 30 31 32. 33 34 J. Halp
Page 26 and 27: 26 Fig. 4.1 kclide Chains Used in b
Page 28 and 29: ’ 28 Table 4.1 Yield F’ractions
Page 30 and 31: 7.5249"7 30 Table 4.3 Fission Produ
Page 32 and 33: 32 Table 4.5 (cont'd) U kclide .,(Z
Page 34 and 35: I The infinite-medium code M-GAM wa
Page 37 and 38: Table 5.1. Figure 5.1Materials Zone
Page 39 and 40: 39 Table 5.3. (cont'd) Nuclide Pure
Page 41 and 42: * u E of these dips and elastic res
Page 44 and 45: i 44 6. TWO-DmIONAL CAICULDIONS The
Page 46 and 47: 46 !Cable 6.1 Region Composition a
Page 48 and 49: 48 Table 6.3 Region Neutron Balance
Page 51 and 52: References. 1. D. RI Vondy, T. B. F
Page 53 and 54:
53 Table 7.1 Neutron Balance by Nuc
Page 55 and 56:
,- i 55 i !
Page 57 and 58:
~ . -. I . . ... ) ~ ,..I ........
Page 59:
A DISTRIBUTIOl 1-5. DTIE, OR 6-15.
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Review of Molten Salt Reactor Physics Calculations [Disc 2]

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