International Reactor Dosimetry File 2002 - IAEA Publications

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neutron yield substantially. Furthermore, the neutron energy distributions vary with the angle between the incoming deuteron beam and the location of the measurement. Consequently, these effects lead to a predictable distribution of neutron energies around 14 MeV for all of the experimental data. After an examination of the available experimental neutron data, these experimental data were plotted in the range of 13.5–15.0 MeV. The experimental data were taken from EXFOR, which is available on the IAEA web site as the Nuclear Reaction Database Retrieval System [5.5]. Cross-section evaluations were taken from 640 group representations processed by the IAEA Nuclear Data Section. Available experimental data in the 13.5–15 MeV region exhibited excessive scatter, and therefore selection criteria were applied to the data to be plotted as outlined below: (a) (b) (c) (d) Experimental data were taken directly from EXFOR in many cases. However, while preparing the various cross-section evaluations, the original cross-section evaluators examined all the data in more detail, and then renormalized them on the basis of changes in the monitor reaction cross-sections made after the original measurements were performed and reported. While there was insufficient time to perform this task for all of the reactions in IRDF-2002, Zolotarev provided evaluated and renormalized data for a number of reactions, as indicated in the discussion given below. Comparisons of the raw data and their normalized data show significant reductions in the scatter of data for most cases, as would be expected. Data that vary from most of the other data by significantly more than the stated uncertainties were omitted for clarity in the plots. Where only a few data measurements were available, no data were omitted. Data with very large energy uncertainties or poor energy resolution were generally omitted. Such data can be difficult to interpret, especially for reactions in which the cross-section is rapidly changing in the 14 MeV energy region (such data are more integral than differential in nature). Data published prior to 1970 were frequently omitted because they were superseded by more recent measurements of much higher quality. Again, no data were omitted when only a few measurements were available. Data omission is generally not the best practice, but the agreement between the data and cross-section evaluations implies that the earlier evaluations involved similar data selections. All available data can be plotted using the EXFOR software whenever rapid assessment is considered necessary. Most of the plots are presented on expanded linear scales with suppressed 47
zeros in order to show the relatively small differences between the various cross-section evaluations. The list of reactions and cross-section evaluations is given in Table 5.1. Symbol X indicates that plots were prepared and/or cross-sections were evaluated from the various data libraries; N indicates that no experimental data were available at 14 MeV and consequently plots were not prepared; D denotes that some of the cross-section files were duplicates of the cross-sections found in IRDF-90. 5.2. DETAILED COMMENTS ON THE CANDIDATE CROSS-SECTION LIBRARIES NEAR 14 MeV Detailed comments are provided below for each of the plots shown in Appendix IV. IRDF means IRDF-90, JENDL is JENDL/D-99, RRDF refers to either RRDF-98 or new evaluations, ENDF is ENDF/B-VI, and JEFF refers to JEFF-3.0. — 6 Li(n,α) 3 H and 10 B(n,α) 7 Li: No experimental data were available in EXFOR, and therefore no plots were prepared. — 19 F(n,2n) 18 F: Experimental data were evaluated and renormalized by Zolotarev. Evaluated cross-section files were available in JENDL and the RRDF. The RRDF-98 file clearly gives the best fit to the data with the lowest uncertainties. — 24 Mg(n,p) 24 Na: The IRDF and JENDL are very similar, and both agree well with the data. — 27 Al(n,p) 27 Mg: Experimental data were evaluated and renormalized by Zolotarev. The IRDF, JENDL and new RRDF evaluations are very similar and appear to be slightly lower than most of the experimental data. — 27 Al(n,α) 24 Na: JENDL is a duplicate of the IRDF, which fits the data reasonably well. — 31 P(n,p) 31 Si: The IRDF and JENDL are nearly identical and fit the data equally well, although there is one data point that appears to be discrepant and should probably be rejected. — 32 S(n,p) 32 P: The IRDF was the only file available and the cross-section fits the data quite well, neglecting one apparently discrepant data point. — 45 Sc(n,γ) 46 Sc: The IRDF was the only file available. Neglecting a data point with very high uncertainties, the evaluation fits the data reasonably well. 48
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INTERNATIONAL REACTOR DOSIMETRY FIL
Page 4 and 5:
TECHNICAL REPORTS SERIES No. 452 IN
Page 6 and 7:
FOREWORD An accurate and complete k
Page 9 and 10: Contributing authors O. Bersillon C
Page 11 and 12: 5.1. Plots of experimental data and
Page 14 and 15: 1. INTRODUCTION R. Paviotti-Corcuer
Page 16 and 17: (b) (c) Pointwise data: (i) All dos
Page 18 and 19: REFERENCES TO SECTION 1 [1.1] ZIJP,
Page 20 and 21: cross-sections, and as a consequenc
Page 22 and 23: TABLE 2.1. MEASURED AND CALCULATED
Page 24 and 25: TABLE 2.2. MEASURED AND CALCULATED
Page 26 and 27: [2.24] KOBAYASHI, K., KIMURA, I., M
Page 28 and 29: from ENDF/B-VI Release 8, JEFF-3.0
Page 30 and 31: TABLE 3.1. REACTIONS FROM THE VARIO
Page 32 and 33: Fluence rate per unit energy (m -2
Page 34 and 35: TABLE 3.2. COMPARISON OF THE INTEGR
Page 36 and 37: — 10 B(n,α) 7 Li and 6 Li(n,t) 4
Page 38 and 39: TABLE 3.3. THERMAL NEUTRON CROSS-SE
Page 40 and 41: TABLE 3.4. RELATIVE STANDARD DEVIAT
Page 42 and 43: [3.14] HOLDEN, N.E., “Neutron sca
Page 44 and 45: The rigorous inclusion of all uncer
Page 46 and 47: TABLE 4.1. C/E VALUES IN THE CALIFO
Page 48 and 49: TABLE 4.3. IRDF-90.2 ( DATA IN A CA
Page 50 and 51: TABLE 4.3. IRDF-90.2 ( DATA IN A CA
Page 52 and 53: TABLE 4.4. JENDL/D-99 ( DATA IN A C
Page 54 and 55: TABLE 4.4. JENDL/D-99 ( DATA IN A C
Page 56 and 57: TABLE 4.5. UPDATED RRDF-98 ( DATA I
Page 58 and 59: REFERENCES TO SECTION 4 [4.1] KOCHE
Page 62 and 63: TABLE 5.1. CROSS-SECTION EVALUATION
Page 64 and 65: TABLE 5.1. CROSS-SECTION EVALUATION
Page 66 and 67: — 58 Ni(n,2n) 57 Ni: The IRDF, JE
Page 68 and 69: — 238 U(n,γ) 239 U(β - ) 239 Np
Page 70 and 71: (i) (ii) (iii) (iv) (v) Only diagon
Page 72 and 73: TABLE 6.1. INTEGRAL CHARACTERISTICS
Page 74 and 75: TABLE 6.1. INTEGRAL CHARACTERISTICS
Page 76 and 77: TABLE 6.2. CROSS-SECTIONS IN IRDF-2
Page 84 and 85: 7. CONSISTENCY TEST OF THE CROSS-SE
Page 86 and 87: TABLE 7.1. REFERENCE NEUTRON FIELDS
Page 88 and 89: Fluence, (E) (MeV -1 ) 10 7 10 6 10
Page 90 and 91: TABLE 7.2. SPECTRUM AVERAGED DOSIME
Page 92 and 93: testing of electronic components an
Page 94 and 95: Table 7.3 details the 34 dosimetry
Page 96 and 97: 7.2. RESULTS OF CONSISTENCY TESTING
Page 98 and 99: TABLE 7.4. RATIO OF SPECTRUM AVERAG
Page 104 and 105: [7.7] SEKINE, T., MAEDA, S., AOYAMA
Page 106 and 107: ecommendations found in ASTM practi
Page 108 and 109: 10 2 Damage (MeV· mb) 10 1 10 0 10
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10 2 Damage (MeV· mb) 10 1 10 0 10
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9. DECAY DATA AND ISOTOPIC ABUNDANC
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9.1.4. Data processing The required
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Protactinium-231 is stated to have
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TABLE I.1. METROLOGY REACTIONS (ACT
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For the convenience of the metrolog
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Such approximate calculations are n
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of each neutron energy group. These
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activation rate for the product iso
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III.1. THERMAL CROSS-SECTIONS Gener
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TABLE III.1. COMPARISON OF THERMAL
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TABLE III.2. COMPARISON OF CAPTURE
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TABLE III.3. COMPARISON OF THE Q 0
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— 50 Cr: Compared with the Mughab
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REFERENCES TO APPENDIX III [III.1]
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CONTRIBUTORS TO DRAFTING AND REVIEW
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CONTRIBUTORS TO DRAFTING AND REVIEW
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