International Reactor Dosimetry File 2002 - IAEA Publications

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Contributing authors O. Bersillon Commissariat à l’énergie atomique, Bruyères-le-Châtel, France L.R. Greenwood P.J. Griffin Pacific Northwest Laboratory, United States of America Sandia National Laboratories, United States of America W. Mannhart Physikalisch-Technische Bundesanstalt, Germany H.J. Nolthenius Institute of Nuclear Techniques, Budapest University of Technology and Economics, Hungary R. Paviotti-Corcuera International Atomic Energy Agency K.I. Zolotarev E.M. Zsolnay Institute of Physics and Power Engineering, Russian Federation Institute of Nuclear Techniques, Budapest University of Technology and Economics, Hungary Technical assistance P.K. McLaughlin International Atomic Energy Agency A. Trkov International Atomic Energy Agency
Page 2 and 3: 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 10 and 11: CONTENTS 1. INTRODUCTION . . . . .
Page 12: 9.1.4. Data processing . . . . . .
Page 15 and 16: (b) (c) (d) (e) RRDF-98, and the mo
Page 17 and 18: TABLE 1.1. CONTENTS OF IRDF-2002, A
Page 19 and 20: 2. NEW RUSSIAN EVALUATIONS FOR IRDF
Page 21 and 22: eactions from the unresolved resona
Page 23 and 24: TABLE 2.2. MEASURED AND CALCULATED
Page 25 and 26: [2.9] BADIKOV, S., RABOTNOV, N., ZO
Page 27 and 28: 3. SELECTION OF CANDIDATE CROSS-SEC
Page 29 and 30: 3.2. PRELIMINARY SELECTION OF CROSS
Page 31 and 32: eaction by the Japanese evaluators
Page 33 and 34: TABLE 3.2. COMPARISON OF THE INTEGR
Page 35 and 36: comparing the data with experimenta
Page 37 and 38: — 241 Am(n,f): No up to date expe
Page 39 and 40: TABLE 3.3. THERMAL NEUTRON CROSS-SE
Page 41 and 42: REFERENCES TO SECTION 3 [3.1] PAVIO
Page 43 and 44: 4. RESPONSE OF ACTIVATION REACTIONS
Page 45 and 46: TABLE 4.1. C/E VALUES IN THE CALIFO
Page 47 and 48: TABLE 4.2. C/E VALUES IN THE CALIFO
Page 49 and 50: TABLE 4.3. IRDF-90.2 ( DATA IN A CA
Page 51 and 52: TABLE 4.4. JENDL/D-99 ( DATA IN A C
Page 53 and 54: TABLE 4.4. JENDL/D-99 ( DATA IN A C
Page 55 and 56: TABLE 4.5. UPDATED RRDF-98 ( DATA I
Page 57 and 58: TABLE 4.6. ENDF/B-VI AND JEFF-3.0 (
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5. EVALUATION OF CROSS-SECTIONS AT
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zeros in order to show the relative
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TABLE 5.1. CROSS-SECTION EVALUATION
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52 —Ti(n,x) 48 Sc: Only one data
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54 — 103 Rh(n,n′) 103 Rh m : Ex
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6. FINAL SELECTION OF CROSS-SECTION
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TABLE 6.1. INTEGRAL CHARACTERISTICS
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TABLE 6.1. INTEGRAL CHARACTERISTICS
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TABLE 6.2. CROSS-SECTIONS IN IRDF-2
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REFERENCES TO SECTION 6 [6.1] GRIFF
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covariance file is folded with the
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large test fixtures and provides go
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spectrum for this field [7.12]. A h
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TABLE 7.2. SPECTRUM AVERAGED DOSIME
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Diff. number spectrum, F(E) Neutron
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TABLE 7.3. SPECTRUM AVERAGED DOSIME
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TABLE 7.4. RATIO OF SPECTRUM AVERAG
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7.3. SUMMARY OF THE VALIDATION IRDF
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8. RADIATION DAMAGE FILES AND COMPU
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more sensitive than volume effect d
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Damage efficiency (fraction) 1.00 0
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[8.9] GRIFFIN, P.J., KELLY, J.G., L
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9.1.2. Type of data In addition to
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(a) (b) (c) (d) The overall energy
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Appendix I CONTENTS AND MAT (MATERI
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TABLE I.1. METROLOGY REACTIONS (ACT
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Appendix II NEUTRON SELF-SHIELDING,
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cross-sections in this manner, the
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Burnup is defined as the nuclear tr
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Appendix III COMPARISON OF THERMAL
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TABLE III.1. COMPARISON OF THERMAL
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III.2. Q 0 VALUES Only the values t
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— 93 Nb: There is good agreement
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TABLE III.3. COMPARISON OF THE Q 0
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TABLE III.4. CANDIDATE EVALUATED DA
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Appendix IV PLOTS OF CANDIDATE CROS
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