Review of Molten Salt Reactor Physics Calculations [Disc 2]

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References. 1. D. RI Vondy, T. B. Fowler, M. L. Tbbla$, React& Depletion Code A&AULT (Two-Dimensitial, Multi-Neutron-Group, -Diffusion), O&L- m-1302, March 1966.
Page 1 and 2: OAK RIDGE NATIONAL LABORATORY opero
Page 3: 3 . CONTENTS Intmduction ..........
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 52 and 53: 52 7. DEPIJEPIOI? CUULATIoIdS The p
Page 54 and 55: - 54 maintain criticality. Leakage
Page 56 and 57: . d E ,--. .
Page 58 and 59: The equilibrium cycle calculation w

Review of Molten Salt Reactor Physics Calculations [Disc 2]

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