The JEFF-3.0 Nuclear Data Library

Data Bank ISBN 92-64-01046-7 The JEFF-3.0 Nuclear Data Library JEFF Report 19 Synopsis of the General Purpose File OECD 2005 NEA No. 3711 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT

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FOREWORD The Joint Evaluated Fission and Fusion (JEFF) project is a collaborative effort among NEA Data Bank member countries to develop a reference nuclear data library for use in different nuclear energy applications. The third, improved version of the JEFF general-purpose data library (JEFF-3.0) was recently released. This library contains evaluated nuclear data for 340 materials from 1-H-1 to 99-Es-255. The present report describes the content of this library. 3

TABLE OF CONTENTS Foreword... 3 Introduction... 7 Content of the JEFF-3.0 library... 7 Origin of the JEFF-3.0 evaluations... 8 Library testing and quality assurance... 8 References... 11 Figures... 13 Tables... 17 Annex 1... 125 Annex 2... 127 5

Introduction The Joint Evaluated Fission and Fusion File (JEFF) Project is a collaborative effort involving the member countries of the OECD Nuclear Energy Agency Data Bank. The project provides a framework for co-operative activities between participating countries while seeking to make the most rational and efficient use of the available resources. As with other NEA activities, participation is on a voluntary basis, and each participating organisation is responsible for covering the cost of its own contributions. This project brings together experts in different areas such as measurements, evaluations, file processing and verification and validation of nuclear data. The compilation of the data is mainly performed at the NEA Data Bank under strict quality assurance procedures. The project also maintains close links with other similar international efforts or projects aimed at producing evaluated nuclear data, for example through active participation in the NEA Nuclear Science Committee Working Party on International Nuclear Data Evaluation Co-operation (WPEC). The flow chart in Figure 1 shows the organisation of the JEFF project. In the past, two different evaluated data libraries were produced from two separate groups in the Data Bank member countries: the JEF library and the EFF library. The JEF library addressed the needs of fission applications, while the EFF library was mainly concerned with fusion technology studies. The difference in the application areas is reflected in the content of these libraries and in their validation. The set of materials in the EFF-2.4 [1] library is a subset of the JEF library, but the evaluations are in many cases improvements compared to those of [2], especially for the structural materials and nuclides that are of special interest to fusion (Li, Be, etc.). The JEF and EFF projects worked closely together, but with different time scales, as illustrated in Figure 2. They now co-operate to produce a single new library, JEFF-3. Content of the JEFF-3.0 library The JEFF-3.0 library comprises at present only a general-purpose library, including thermal scattering law data for five materials. This general-purpose library was released in April 2002 and contains data for 340 materials from 1-H-1 to 99-Es-255. Table 1 provides the list of materials in the library. A material corresponds to a nucleus of a single isotope or to a nucleus of a natural element. A nucleus is either in its ground state or in an isomeric state. In the first column of Table 1, the material is represented as ZZZ-SY-AAA where AAA and ZZZ are the atomic charge and mass given as three-digit integers. SY is the symbol of the material represented with two characters. Note that AAA is equal to zero when the material represents a natural element. In addition, when the nucleus is in its first isomeric state, the letter m is appended to the end of the column (e.g. 95-Am-242m). The materials are classified in ascending atomic charge order. The second column provides the material number used to identify the isotope or the element in the library. The third column gives the name of the file, which contains the evaluated data for this specific material and which can be found on the enclosed CD-ROM. The last five materials in the table represent neutron thermal scattering data for the following compounds: hydrogen in light water, deuterium in heavy water, beryllium in beryllium oxide, carbon in graphite and hydrogen in polyethylene. The JEFF-3.0 library is given in the ENDF-6 format. This format stores nuclear data in various sections (MF). Each file contains data for different reactions (MT). Annexes 1 and 2 give the list of MF and MT numbers and their meaning in the ENDF-6 format. 7

Table 2 provides details concerning the content of each evaluated file. Reactions for which cross-section data is given in File 3 (MF=3) are listed in the second column. The reactions are listed using ENDF-6 nomenclature. This nomenclature is briefly described in Annex 1. Columns 3 through 5 list the reactions for which angular distributions, energy distributions or energy-angle distributions are given in File 4, 5 or 6 (MF=4, 5 or 6). Table 3 gives a list of materials for which resonance data is give in File 2 (MF=2). This table includes information about the formalism used in the resolved resonance region, the energy limits of the different resonance regions and a list of the energies of the first three s-wave resonances. Table 4 gives a list of materials for which photon production data is available in Files 12 to 15 (MF=12 to 15). Table 5 provides a list of materials for which covariance data is available in Files 31 through 35 (MF=31 to 35). Origin of the JEFF-3.0 evaluations The choice of evaluated data was guided by the feedback accumulated from the validation of the and EFF-2.4 libraries. Consequently, and EFF-2.4 formed the basic skeletons of the JEFF-3.0 library. Other evaluated files (e.g. JENDL-3.2, ENDF/B-VI, CENDL-2.1 or BROND-2.2) were adopted when data were not available in the JEF(F) libraries or when other evaluated files where considered to be of better quality. New evaluated files were also created for JEFF-3.0 (e.g. Be, Si, V, Ni, Cr, Fe, 240 Pu). Finally, modifications to existing files were made to obtain better agreement with integral data (e.g. 143 Nd, 149 Sm, 238 U and 241 Pu). Table 6 lists the origin of all evaluated files in the JEFF-3.0 library. The general recommendations for the selection of files for JEFF-3.0 are described in Ref. [1]. Adjustments to these choices were made for specific nuclides. The corresponding references are given below: x Aluminium [2]. x Fission products [3-5]. x x x 239 Pu [6,7]. 240 Pu [8]. 241 Pu [9]. x Energy release in fission [10]. x Photon production data [11]. Library testing and quality assurance The JEFF-3.0 starter file has undergone thorough testing at the NEA Data Bank. The tests were performed according to recently developed QA procedures, which included running the BNL checking 8

codes (CHECKER, FIZCON and PSYCHE) on every evaluated data set. The results of the checking codes are given in the CD-ROM appended to this report. In addition, the files were processed with the latest version of NJOY. Integral data, such as Maxwellian average cross-sections and resonance integrals, were also generated using the INTER code version 6.12. The temperature used was 293 K and E 0 = 0.0253 ev for the thermal spectrum temperature. The results were compared to those of. This test helped identify and correct a few inconsistencies, which had not been detected by the QA checks. The JEFF-3.0 integral data can be found in Table 7. The feedback emerging from JEFF-3.0 testing and processing is available on the following website: http://www.nea.fr/html/dbdata/jeff3feedback/welcome.html. Refs. [12-14] provide more details as concerns this feedback. 9

REFERENCES Electronic copies of the JEF/DOC documents below are included in the CD-ROM appended to the paper version of this report. [1] Rowlands, J.L., Proposed Selection of Data for JEFF-3, JEFDOC-657. [2] Leal, L.C., et al., Aluminium Data Measurements and Evaluation for Criticality Safety Applications, JEFDOC-913. [3] Chabert, C., A. Courcelle, B. Roque, O. Serot, Progress Report on Main FPs Qualification. Recommendation for 154 Eu, 155 Eu, 143 Nd and 149 Sm, JEFDOC-885. [4] Serot, O., et al., 133 Cs Fission Product: Recommendation for JEFF3, JEFDOC-874. [5] Serot, O., et al., Progress Report on Main Fission Products: Recommendations for 103 Rh, 152 Eu and 153 Eu, JEF/DOC-912. [6] Romain, P., et al., New Evaluation of 239 Pu Data, JEF/DOC-919. [7] Serot, O., B. Morillon, E. Fort, Energy Release in Thermal Neutron Induced Fission of 239 Pu, JEF/DOC-900. [8] Courcelle, A., A. Santamarina, C. Chabert, O. Litaize, Validation of the Current 241 Pu Evaluations Against Integral Experiments. Proposed JEFF3.0 Evaluation, JEF/DOC-884. [9] Derrien, H., A. Courcelle, A. Santamarina, Re-evaluation and Validation of the 241 Pu Resonance Parameters in the Energy Range Thermal to 20 ev, JEF/DOC-916. [10] Serot, O., A. Courcelle, Energy Released in Fission: Short Review for JEFF3, JEF/DOC-887. [11] Courcelle, A., Gamma Production Data, Prompt Gamma Emitted in Fission: Short Review, JEF/DOC-886. [12] Sublet, J-Ch. and P. Ribon, NJOY99 and CALENDF-2002 Processing Viewpoint, Prospect and Solutions, JEFDOC-934. [13] Nouri, A., JEFF-3.0 Feedback: Status April 2003, JEFDOC-967. [14] Sublet, J-Ch., B. Roque, F. Laugier, J. Tommasi, JEFF-3.0 Feedbacks Pre-JEFF-3.1 Proposals, JEF/DOC-1011. 11

FIGURES 13

Figure 1. Organisation of the project Figure 2. Time scales of the JEF and EFF projects 15

TABLES 17

Table 1. List of materials in the JEFF-3.0 library Nuclide or element MAT and isomeric state number Evaluation file 1-H-1 125 JEFF30N125_1.ASC 1-H-2 128 JEFF30N128_1.ASC 1-H-3 131 JEFF30N131_1.ASC 2-He-3 225 JEFF30N225_1.ASC 2-He-4 228 JEFF30N228_1.ASC 3-Li-6 325 JEFF30N325_1.ASC 3-Li-7 328 JEFF30N328_1.ASC 4-Be-9 425 JEFF30N425_2.ASC 5-B-10 525 JEFF30N525_1.ASC 5-B-11 528 JEFF30N528_1.ASC 6-C-nat 600 JEFF30N600_1.ASC 7-N-14 725 JEFF30N725_2.ASC 7-N-15 728 JEFF30N728_2.ASC 8-O-16 825 JEFF30N825_1.ASC 8-O-17 828 JEFF30N828_1.ASC 9-F-19 925 JEFF30N925_1.ASC 11-Na-22 1122 JEFF30N1122_1.ASC 11-Na-23 1125 JEFF30N1125_2.ASC 12-Mg-nat 1200 JEFF30N1200_1.ASC 13-Al-27 1325 JEFF30N1325_2.ASC 14-Si-28 1425 JEFF30N1425_4.ASC 14-Si-29 1428 JEFF30N1428_2.ASC 14-Si-30 1431 JEFF30N1431_2.ASC 15-P-31 1525 JEFF30N1525_1.ASC 16-S-nat 1600 JEFF30N1600_2.ASC 17-Cl-nat 1700 JEFF30N1700_1.ASC 18-Ar-36 1825 JEFF30N1825_1.ASC 18-Ar-38 1831 JEFF30N1831_1.ASC 18-Ar-40 1837 JEFF30N1837_1.ASC 19-K-nat 1900 JEFF30N1900_2.ASC 20-Ca-nat 2000 JEFF30N2000_2.ASC 21-Sc-45 2125 JEFF30N2125_1.ASC 22-Ti-nat 2200 JEFF30N2200_1.ASC 23-V-nat 2300 JEFF30N2300_1.ASC 24-Cr-50 2425 JEFF30N2425_1.ASC 24-Cr-52 2431 JEFF30N2431_1.ASC 24-Cr-53 2434 JEFF30N2434_3.ASC 24-Cr-54 2437 JEFF30N2437_3.ASC 25-Mn-55 2525 JEFF30N2525_1.ASC 26-Fe-54 2625 JEFF30N2625_1.ASC 26-Fe-56 2631 JEFF30N2631_2.ASC 19

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 26-Fe-57 2634 JEFF30N2634_1.ASC 26-Fe-58 2637 JEFF30N2637_1.ASC 27-Co-58 2722 JEFF30N2722_3.ASC 27-Co-58m 2723 JEFF30N2723_2.ASC 27-Co-59 2725 JEFF30N2725_1.ASC 28-Ni-58 2825 JEFF30N2825_2.ASC 28-Ni-59 2828 JEFF30N2828_1.ASC 28-Ni-60 2831 JEFF30N2831_2.ASC 28-Ni-61 2834 JEFF30N2834_1.ASC 28-Ni-62 2837 JEFF30N2837_1.ASC 28-Ni-64 2843 JEFF30N2843_1.ASC 29-Cu-63 2925 JEFF30N2925_1.ASC 29-Cu-65 2931 JEFF30N2931_1.ASC 30-Zn-nat 3000 JEFF30N3000_1.ASC 31-Ga-nat 3100 JEFF30N3100_1.ASC 32-Ge-70 3225 JEFF30N3225_1.ASC 32-Ge-72 3231 JEFF30N3231_1.ASC 32-Ge-73 3234 JEFF30N3234_1.ASC 32-Ge-74 3237 JEFF30N3237_1.ASC 32-Ge-76 3243 JEFF30N3243_1.ASC 33-As-75 3325 JEFF30N3325_1.ASC 34-Se-74 3425 JEFF30N3425_1.ASC 34-Se-76 3431 JEFF30N3431_2.ASC 34-Se-77 3434 JEFF30N3434_1.ASC 34-Se-78 3437 JEFF30N3437_1.ASC 34-Se-79 3440 JEFF30N3440_1.ASC 34-Se-80 3443 JEFF30N3443_1.ASC 34-Se-82 3449 JEFF30N3449_1.ASC 35-Br-79 3525 JEFF30N3525_1.ASC 35-Br-81 3531 JEFF30N3531_1.ASC 36-Kr-78 3625 JEFF30N3625_1.ASC 36-Kr-80 3631 JEFF30N3631_1.ASC 36-Kr-82 3637 JEFF30N3637_1.ASC 36-Kr-83 3640 JEFF30N3640_1.ASC 36-Kr-84 3643 JEFF30N3643_1.ASC 36-Kr-85 3646 JEFF30N3646_1.ASC 36-Kr-86 3649 JEFF30N3649_1.ASC 37-Rb-85 3725 JEFF30N3725_1.ASC 37-Rb-86 3728 JEFF30N3728_1.ASC 37-Rb-87 3731 JEFF30N3731_1.ASC 38-Sr-84 3825 JEFF30N3825_1.ASC 20

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 38-Sr-86 3831 JEFF30N3831_1.ASC 38-Sr-87 3834 JEFF30N3834_1.ASC 38-Sr-88 3837 JEFF30N3837_1.ASC 38-Sr-89 3840 JEFF30N3840_1.ASC 38-Sr-90 3843 JEFF30N3843_1.ASC 39-Y-89 3925 JEFF30N3925_1.ASC 39-Y-90 3928 JEFF30N3928_1.ASC 39-Y-91 3931 JEFF30N3931_1.ASC 40-Zr-90 4025 JEFF30N4025_1.ASC 40-Zr-91 4028 JEFF30N4028_1.ASC 40-Zr-92 4031 JEFF30N4031_1.ASC 40-Zr-93 4034 JEFF30N4034_2.ASC 40-Zr-94 4037 JEFF30N4037_1.ASC 40-Zr-95 4040 JEFF30N4040_1.ASC 40-Zr-96 4043 JEFF30N4043_1.ASC 41-Nb-93 4125 JEFF30N4125_1.ASC 42-Mo-92 4225 JEFF30N4225_2.ASC 42-Mo-94 4231 JEFF30N4231_2.ASC 42-Mo-95 4234 JEFF30N4234_2.ASC 42-Mo-96 4237 JEFF30N4237_2.ASC 42-Mo-97 4240 JEFF30N4240_2.ASC 42-Mo-98 4243 JEFF30N4243_2.ASC 42-Mo-99 4246 JEFF30N4246_1.ASC 42-Mo-100 4249 JEFF30N4249_2.ASC 43-Tc-99 4331 JEFF30N4331_1.ASC 44-Ru-96 4425 JEFF30N4425_1.ASC 44-Ru-98 4431 JEFF30N4431_1.ASC 44-Ru-99 4434 JEFF30N4434_1.ASC 44-Ru-100 4437 JEFF30N4437_1.ASC 44-Ru-101 4440 JEFF30N4440_1.ASC 44-Ru-102 4443 JEFF30N4443_1.ASC 44-Ru-103 4446 JEFF30N4446_1.ASC 44-Ru-104 4449 JEFF30N4449_1.ASC 44-Ru-105 4452 JEFF30N4452_1.ASC 44-Ru-106 4455 JEFF30N4455_1.ASC 45-Rh-103 4525 JEFF30N4525_2.ASC 45-Rh-105 4531 JEFF30N4531_1.ASC 46-Pd-102 4625 JEFF30N4625_1.ASC 46-Pd-104 4631 JEFF30N4631_1.ASC 46-Pd-105 4634 JEFF30N4634_1.ASC 46-Pd-106 4637 JEFF30N4637_1.ASC 21

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 46-Pd-107 4640 JEFF30N4640_1.ASC 46-Pd-108 4643 JEFF30N4643_1.ASC 46-Pd-110 4649 JEFF30N4649_1.ASC 47-Ag-107 4725 JEFF30N4725_1.ASC 47-Ag-109 4731 JEFF30N4731_1.ASC 47-Ag-111 4737 JEFF30N4737_1.ASC 48-Cd-106 4825 JEFF30N4825_1.ASC 48-Cd-108 4831 JEFF30N4831_1.ASC 48-Cd-110 4837 JEFF30N4837_1.ASC 48-Cd-111 4840 JEFF30N4840_1.ASC 48-Cd-112 4843 JEFF30N4843_1.ASC 48-Cd-113 4846 JEFF30N4846_1.ASC 48-Cd-114 4849 JEFF30N4849_1.ASC 48-Cd-115m 4853 JEFF30N4853_1.ASC 48-Cd-116 4855 JEFF30N4855_1.ASC 49-In-113 4925 JEFF30N4925_1.ASC 49-In-115 4931 JEFF30N4931_1.ASC 50-Sn-112 5025 JEFF30N5025_1.ASC 50-Sn-114 5031 JEFF30N5031_1.ASC 50-Sn-115 5034 JEFF30N5034_1.ASC 50-Sn-116 5037 JEFF30N5037_1.ASC 50-Sn-117 5040 JEFF30N5040_1.ASC 50-Sn-118 5043 JEFF30N5043_1.ASC 50-Sn-119 5046 JEFF30N5046_1.ASC 50-Sn-120 5049 JEFF30N5049_1.ASC 50-Sn-122 5055 JEFF30N5055_1.ASC 50-Sn-123 5058 JEFF30N5058_1.ASC 50-Sn-124 5061 JEFF30N5061_1.ASC 50-Sn-125 5064 JEFF30N5064_1.ASC 50-Sn-126 5067 JEFF30N5067_1.ASC 51-Sb-121 5125 JEFF30N5125_2.ASC 51-Sb-123 5131 JEFF30N5131_2.ASC 51-Sb-124 5134 JEFF30N5134_1.ASC 51-Sb-125 5137 JEFF30N5137_1.ASC 51-Sb-126 5140 JEFF30N5140_1.ASC 52-Te-120 5225 JEFF30N5225_1.ASC 52-Te-122 5231 JEFF30N5231_1.ASC 52-Te-123 5234 JEFF30N5234_1.ASC 52-Te-124 5237 JEFF30N5237_1.ASC 52-Te-125 5240 JEFF30N5240_1.ASC 52-Te-126 5243 JEFF30N5243_1.ASC 22

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 52-Te-127m 5247 JEFF30N5247_1.ASC 52-Te-128 5249 JEFF30N5249_1.ASC 52-Te-129m 5253 JEFF30N5253_1.ASC 52-Te-130 5255 JEFF30N5255_1.ASC 52-Te-132 5261 JEFF30N5261_1.ASC 53-I-127 5325 JEFF30N5325_1.ASC 53-I-129 5331 JEFF30N5331_1.ASC 53-I-130 5334 JEFF30N5334_1.ASC 53-I-131 5337 JEFF30N5337_1.ASC 53-I-135 5349 JEFF30N5349_1.ASC 54-Xe-124 5425 JEFF30N5425_1.ASC 54-Xe-126 5431 JEFF30N5431_1.ASC 54-Xe-128 5437 JEFF30N5437_1.ASC 54-Xe-129 5440 JEFF30N5440_1.ASC 54-Xe-130 5443 JEFF30N5443_1.ASC 54-Xe-131 5446 JEFF30N5446_1.ASC 54-Xe-132 5449 JEFF30N5449_1.ASC 54-Xe-133 5452 JEFF30N5452_1.ASC 54-Xe-134 5455 JEFF30N5455_1.ASC 54-Xe-135 5458 JEFF30N5458_1.ASC 54-Xe-136 5461 JEFF30N5461_1.ASC 55-Cs-133 5525 JEFF30N5525_2.ASC 55-Cs-134 5528 JEFF30N5528_1.ASC 55-Cs-135 5531 JEFF30N5531_1.ASC 55-Cs-136 5534 JEFF30N5534_1.ASC 55-Cs-137 5537 JEFF30N5537_1.ASC 56-Ba-130 5625 JEFF30N5625_1.ASC 56-Ba-132 5631 JEFF30N5631_1.ASC 56-Ba-134 5637 JEFF30N5637_1.ASC 56-Ba-135 5640 JEFF30N5640_1.ASC 56-Ba-136 5643 JEFF30N5643_1.ASC 56-Ba-137 5646 JEFF30N5646_1.ASC 56-Ba-138 5649 JEFF30N5649_1.ASC 56-Ba-140 5655 JEFF30N5655_1.ASC 57-La-138 5725 JEFF30N5725_1.ASC 57-La-139 5728 JEFF30N5728_1.ASC 57-La-140 5731 JEFF30N5731_1.ASC 58-Ce-140 5837 JEFF30N5837_1.ASC 58-Ce-141 5840 JEFF30N5840_1.ASC 58-Ce-142 5843 JEFF30N5843_1.ASC 58-Ce-143 5846 JEFF30N5846_1.ASC 23

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 58-Ce-144 5849 JEFF30N5849_1.ASC 59-Pr-141 5925 JEFF30N5925_1.ASC 59-Pr-142 5928 JEFF30N5928_1.ASC 59-Pr-143 5931 JEFF30N5931_1.ASC 60-Nd-142 6025 JEFF30N6025_1.ASC 60-Nd-143 6028 JEFF30N6028_2.ASC 60-Nd-144 6031 JEFF30N6031_1.ASC 60-Nd-145 6034 JEFF30N6034_1.ASC 60-Nd-146 6037 JEFF30N6037_1.ASC 60-Nd-147 6040 JEFF30N6040_1.ASC 60-Nd-148 6043 JEFF30N6043_1.ASC 60-Nd-150 6049 JEFF30N6049_1.ASC 61-Pm-147 6149 JEFF30N6149_2.ASC 61-Pm-148 6152 JEFF30N6152_1.ASC 61-Pm-148m 6153 JEFF30N6153_1.ASC 61-Pm-149 6155 JEFF30N6155_1.ASC 61-Pm-151 6161 JEFF30N6161_1.ASC 62-Sm-144 6225 JEFF30N6225_1.ASC 62-Sm-147 6234 JEFF30N6234_1.ASC 62-Sm-148 6237 JEFF30N6237_1.ASC 62-Sm-149 6240 JEFF30N6240_2.ASC 62-Sm-150 6243 JEFF30N6243_1.ASC 62-Sm-151 6246 JEFF30N6246_1.ASC 62-Sm-152 6249 JEFF30N6249_1.ASC 62-Sm-153 6252 JEFF30N6252_1.ASC 62-Sm-154 6255 JEFF30N6255_1.ASC 63-Eu-151 6325 JEFF30N6325_2.ASC 63-Eu-152 6328 JEFF30N6328_2.ASC 63-Eu-153 6331 JEFF30N6331_2.ASC 63-Eu-154 6334 JEFF30N6334_2.ASC 63-Eu-155 6337 JEFF30N6337_2.ASC 63-Eu-156 6340 JEFF30N6340_1.ASC 63-Eu-157 6343 JEFF30N6343_1.ASC 64-Gd-152 6425 JEFF30N6425_1.ASC 64-Gd-154 6431 JEFF30N6431_1.ASC 64-Gd-155 6434 JEFF30N6434_1.ASC 64-Gd-156 6437 JEFF30N6437_1.ASC 64-Gd-157 6440 JEFF30N6440_1.ASC 64-Gd-158 6443 JEFF30N6443_1.ASC 64-Gd-160 6449 JEFF30N6449_1.ASC 65-Tb-159 6525 JEFF30N6525_1.ASC 24

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 65-Tb-160 6528 JEFF30N6528_1.ASC 66-Dy-160 6637 JEFF30N6637_1.ASC 66-Dy-161 6640 JEFF30N6640_1.ASC 66-Dy-162 6643 JEFF30N6643_1.ASC 66-Dy-163 6646 JEFF30N6646_1.ASC 66-Dy-164 6649 JEFF30N6649_1.ASC 67-Ho-165 6725 JEFF30N6725_1.ASC 68-Er-162 6825 JEFF30N6825_2.ASC 68-Er-164 6831 JEFF30N6831_1.ASC 68-Er-166 6837 JEFF30N6837_1.ASC 68-Er-167 6840 JEFF30N6840_1.ASC 68-Er-168 6843 JEFF30N6843_2.ASC 68-Er-170 6846 JEFF30N6846_1.ASC 71-Lu-175 7125 JEFF30N7125_1.ASC 71-Lu-176 7128 JEFF30N7128_1.ASC 72-Hf-174 7225 JEFF30N7225_1.ASC 72-Hf-176 7231 JEFF30N7231_1.ASC 72-Hf-177 7234 JEFF30N7234_1.ASC 72-Hf-178 7237 JEFF30N7237_1.ASC 72-Hf-179 7240 JEFF30N7240_1.ASC 72-Hf-180 7243 JEFF30N7243_2.ASC 73-Ta-181 7328 JEFF30N7328_1.ASC 73-Ta-182 7331 JEFF30N7331_2.ASC 74-W-182 7431 JEFF30N7431_2.ASC 74-W-183 7434 JEFF30N7434_2.ASC 74-W-184 7437 JEFF30N7437_2.ASC 74-W-186 7443 JEFF30N7443_2.ASC 75-Re-185 7525 JEFF30N7525_1.ASC 75-Re-187 7531 JEFF30N7531_1.ASC 76-Os-nat 7600 JEFF30N7600_1.ASC 77-Ir-nat 7700 JEFF30N7700_2.ASC 78-Pt-nat 7800 JEFF30N7800_1.ASC 79-Au-197 7925 JEFF30N7925_1.ASC 80-Hg-nat 8000 JEFF30N8000_2.ASC 81-Tl-nat 8100 JEFF30N8100_2.ASC 82-Pb-204 8225 JEFF30N8225_2.ASC 82-Pb-206 8231 JEFF30N8231_3.ASC 82-Pb-207 8234 JEFF30N8234_3.ASC 82-Pb-208 8237 JEFF30N8237_3.ASC 83-Bi-209 8325 JEFF30N8325_1.ASC 90-Th-227 9025 JEFF30N9025_2.ASC 25

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 90-Th-228 9028 JEFF30N9028_2.ASC 90-Th-229 9031 JEFF30N9031_2.ASC 90-Th-230 9034 JEFF30N9034_2.ASC 90-Th-232 9040 JEFF30N9040_2.ASC 90-Th-233 9043 JEFF30N9043_2.ASC 90-Th-234 9046 JEFF30N9046_2.ASC 91-Pa-231 9131 JEFF30N9131_1.ASC 91-Pa-233 9137 JEFF30N9137_2.ASC 92-U-232 9219 JEFF30N9219_1.ASC 92-U-233 9222 JEFF30N9222_2.ASC 92-U-234 9225 JEFF30N9225_1.ASC 92-U-235 9228 JEFF30N9228_3.ASC 92-U-236 9231 JEFF30N9231_1.ASC 92-U-237 9234 JEFF30N9234_2.ASC 92-U-238 9237 JEFF30N9237_4.ASC 93-Np-236 9343 JEFF30N9343_1.ASC 93-Np-237 9346 JEFF30N9346_2.ASC 93-Np-238 9349 JEFF30N9349_1.ASC 93-Np-239 9352 JEFF30N9352_2.ASC 94-Pu-236 9428 JEFF30N9428_2.ASC 94-Pu-237 9431 JEFF30N9431_2.ASC 94-Pu-238 9434 JEFF30N9434_3.ASC 94-Pu-239 9437 JEFF30N9437_3.ASC 94-Pu-240 9440 JEFF30N9440_3.ASC 94-Pu-241 9443 JEFF30N9443_3.ASC 94-Pu-242 9446 JEFF30N9446_2.ASC 94-Pu-243 9449 JEFF30N9449_1.ASC 94-Pu-244 9452 JEFF30N9452_2.ASC 95-Am-241 9543 JEFF30N9543_2.ASC 95-Am-242 9546 JEFF30N9546_3.ASC 95-Am-242m 9547 JEFF30N9547_2.ASC 95-Am-243 9549 JEFF30N9549_2.ASC 95-Am-244 9552 JEFF30N9552_1.ASC 95-Am-244m 9553 JEFF30N9553_1.ASC 96-Cm-241 9628 JEFF30N9628_2.ASC 96-Cm-242 9631 JEFF30N9631_2.ASC 96-Cm-243 9634 JEFF30N9634_2.ASC 96-Cm-244 9637 JEFF30N9637_2.ASC 96-Cm-245 9640 JEFF30N9640_1.ASC 96-Cm-246 9643 JEFF30N9643_1.ASC 96-Cm-247 9646 JEFF30N9646_2.ASC 26

Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 96-Cm-248 9649 JEFF30N9649_3.ASC 96-Cm-249 9652 JEFF30N9652_1.ASC 96-Cm-250 9655 JEFF30N9655_1.ASC 97-Bk-249 9752 JEFF30N9752_2.ASC 97-Bk-250 9755 JEFF30N9755_2.ASC 98-Cf-249 9852 JEFF30N9852_2.ASC 98-Cf-250 9855 JEFF30N9855_1.ASC 98-Cf-251 9858 JEFF30N9858_1.ASC 98-Cf-252 9861 JEFF30N9861_2.ASC 98-Cf-254 9867 JEFF30N9867_1.ASC 99-Es-254 9914 JEFF30N9914_2.ASC 99-Es-255 9915 JEFF30N9915_1.ASC H in H20 thermal scattering data 1 JEFF30TS1_1.ASC D in D20 thermal scattering data 11 JEFF30TS11_1.ASC Be thermal scattering data 26 JEFF30TS26_1.ASC Graphite thermal scattering data 31 JEFF30TS31_1.ASC H in CH2 thermal scattering data 37 JEFF30TS37_1.ASC 27

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 Reactions with energy-angle distributions in MF=6 1 H 1, 2, 102 2 2 H 1, 2, 16, 102 2 16 3 H 1, 2, 16, 17 2, 16 16 17 3 He 1, 2, 102-104 2 4 He 1, 2, 251 2 6 Li 1, 2, 4, 24, 51-81, 102, 103, 105 2, 24, 51-81, 105 24 7 Li 1, 2, 4, 16, 24, 25, 28, 51-53, 91, 102, 104 2, 51, 52 16, 24, 25, 28, 53, 91 9 Be 1-3, 16, 103-105, 107, 875-890 2 16, 107, 875-890 10 B 1, 2, 4, 51-85, 102-104, 107, 113, 600-605, 800, 801 2, 51-85 11 B 1, 2, 4, 16, 22, 28, 51-60, 91, 102, 103, 105, 107 2, 51-60 16, 22, 28, 91, 103, 107 16, 24, 28, 32, 33, 41, 91, nat C 1-4, 16, 24, 28, 32, 33, 41, 51-73, 91, 102-105, 107, 111, 112, 115, 116, 203-205, 207 14 N 1, 2, 4, 16, 51-90, 102-105, 107, 108, 600-606, 650-653, 700, 701, 800-810 2, 16, 24, 28, 32, 33, 41, 51-73, 91 2, 51-90 16 15 N 1, 2, 4, 16, 22, 28, 51-57, 91, 102-105, 107 2, 16, 22, 28, 51-57, 91 16, 22, 28, 91 16 O 1, 2, 4, 51-88, 102-104, 107, 800-803 2, 51-88 17 O 1, 2, 4, 16, 22, 28, 51-62, 91, 102-104, 107 2, 16, 22, 28, 51-62, 91 16, 22, 28, 91 19 F 1-4, 16, 22, 28, 51-71, 91, 102-105, 107 2, 51-71 16, 22, 28, 91, 102, 103, 107 22 Na 1, 2, 4, 16, 22, 28, 51-61, 91, 102-104, 107, 108, 251 2, 16, 22, 28, 51-61, 91 16, 91 23 Na 1, 2, 4, 16, 22, 28, 51-77, 91, 102, 103, 107, 251 2, 16, 22, 28, 51-77, 91 16, 22, 28, 91 nat Mg 1-4, 16, 22, 28, 51-91, 102, 103, 107, 251 2, 16, 22, 28, 51-91 16, 22, 28, 91 27 Al 1-5, 16, 22, 28, 32, 33, 45, 51-89, 91, 102-105, 107, 108, 111, 112, 117, 600-619, 649-669, 699-710, 749, 800-819, 849 28 Si 1-4, 16, 22, 28, 51-67, 91, 102-107, 111, 600-613, 649, 800-815, 849 29 Si 1, 2, 4, 16, 22, 28, 51-79, 91, 102, 103, 107, 111, 251 2, 16, 22, 28, 51-79, 91 16, 22, 28, 91 30 Si 1, 2, 4, 16, 22, 28, 51-69, 91, 102, 103, 107, 111, 251 2, 16, 22, 28, 51-69, 91 16, 22, 28, 91 31 P 1, 2, 4, 16, 22, 28, 51-56, 91, 102, 103, 107, 251 2, 16, 22, 28, 51-56, 91 16, 22, 28, 91 2 5, 16, 22, 28, 32, 33, 45, 51-89, 91, 108, 111, 112, 117, 600-619, 649-669, 699-710, 749, 800-819, 849 2 16, 22, 28, 51-67, 91, 600-613, 649, 800-815, 849 28

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 nat S 1, 2, 4, 16, 22, 28, 51-73, 91, 102, 103, 107, 251 2, 16, 22, 28, 51-73, 91 16, 22, 28, 91 nat Cl 1, 2, 4, 16, 22, 28, 51-63, 91, 102, 103, 107, 251-253 2, 16, 22, 28, 51-63, 91 16, 22, 28, 91 36 Ar 1, 2, 4, 16, 22, 28, 51-71, 91, 102-104, 107, 108, 251, 2, 16, 22, 28, 51-71, 91 16, 91 252 38 Ar 1, 2, 4, 16, 22, 28, 51-69, 91, 102-104, 107, 108, 251, 2, 16, 22, 28, 51-69, 91 16, 91 252 40 Ar 1, 2, 4, 16, 17, 22, 28, 51-71, 91, 102-104, 107, 251, 2, 16, 17, 22, 28, 51-71, 91 16, 17, 91 252 nat K 1, 2, 4, 16, 22, 28, 51-61, 91, 102, 103, 107, 251 2, 16, 22, 28, 51-61, 91 16, 22, 28, 91 nat Ca 1, 2, 4, 16, 17, 22, 28, 51-84, 91, 102, 103, 107, 111, 2, 16, 17, 22, 28, 51-84, 91 16, 17, 22, 28, 91 251 Reactions with energy-angle distributions in MF=6 45 Sc 1, 2, 4, 16, 22, 28, 51-64, 91, 102-107 2, 16, 22, 28, 51-64, 91 16, 22, 28, 91 nat Ti 1, 2, 4, 16, 17, 22, 28, 51-87, 91, 102, 103, 107, 251 2, 16, 17, 22, 28, 51-87, 91 16, 17, 22, 28, 91 nat V 1, 2, 4, 16, 22, 28, 32, 51-74, 91, 102-107, 111, 112 2, 32, 51-74 32 16, 22, 28, 91, 103, 107 50 Cr 1-4, 16, 22, 28, 51-56, 91, 102-104, 107 2 16, 22, 28, 51-56, 91, 103, 107 52 Cr 1-5, 51-66, 102, 600-624, 800-811 2, 51-66, 600-624, 800-811 5 53 Cr 1-4, 16, 22, 28, 51-63, 91, 102, 103, 107 2 16, 22, 28, 51-63, 91, 103, 107 54 Cr 1-4, 16, 51-54, 91, 102, 103, 107 2 16, 51-54, 91, 103, 107 55 Mn 1-4, 16, 22, 28, 51-66, 91, 102-107, 203-207, 251 2, 51-66 16, 22, 28, 91, 203-207 54 Fe 1-4, 16, 22, 28, 51-57, 91, 102-104, 107 2 16, 22, 28, 51-57, 91, 103, 107 56 Fe 1-4, 16, 22, 28, 51-82, 91, 102-107, 600-613, 649, 2, 51-82, 600-613, 800-810 16, 22, 28, 91, 649, 849 800-810, 849 57 Fe 1, 2, 4, 16, 22, 28, 51-65, 91, 102-105, 107, 251 2, 16, 22, 28, 51-65, 91 16, 22, 28, 91 58 Fe 1, 2, 4, 16, 22, 28, 51-67, 91, 102-105, 107, 251 2, 16, 22, 28, 51-67, 91 16, 22, 28, 91 58 Co 1, 2, 4, 16, 22, 28, 51-62, 91, 102-104, 107, 251 2, 16, 22, 28, 51-62, 91 16, 91 58m Co 1, 2, 4, 16, 22, 28, 51-62, 91, 102-104, 107, 251 2, 16, 22, 28, 51-62, 91 16, 91 59 Co 1, 2, 4, 16, 22, 28, 32, 33, 51-69, 91, 102-108, 111, 2, 16, 22, 28, 32, 33, 51-69, 91 16, 22, 28, 32, 33, 91 112 58 Ni 1-4, 16, 22, 28, 51-58, 91, 102-107, 112 2 16, 22, 28, 51-58, 91, 103, 107 29

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 Reactions with energy-angle distributions in MF=6 59 Ni 1-3, 16, 22, 28, 32, 34, 102-107, 111 2, 16, 22, 28, 32, 34 60 Ni 1-4, 16, 22, 28, 51-61, 91, 102-107 2 16, 22, 28, 51-61, 91, 103, 107 61 Ni 1-4, 16, 28, 51-58, 91, 102, 103, 107, 111 2 16, 28, 51-58, 91, 103, 107 62 Ni 1-4, 16, 22, 28, 51-54, 91, 102-104, 107 2 16, 22, 28, 51-54, 91, 103, 107 64 Ni 1-4, 16, 22, 28, 51, 52, 91, 102-104, 107 2 16, 22, 28, 51, 52, 91, 103, 107 63 Cu 1-4, 16, 22, 28, 51-72, 91, 102-104, 106, 107 2 16, 22, 28, 51-72, 91, 103, 107 65 Cu 1-4, 16, 22, 28, 51-63, 91, 102-107 2 16, 22, 28, 51-63, 91, 103, 107 nat Zn 1, 2, 4, 16, 17, 22, 28, 51, 91, 102, 103, 105, 107, 251-253 nat Ga 1, 2, 4, 16, 17, 22, 28, 32, 51-88, 91, 102-107, 111, 251 2, 16, 17, 22, 28, 51, 91 16, 17, 22, 28, 91 2, 16, 17, 22, 28, 32, 51-88, 91 16, 17, 22, 28, 32, 91 70 Ge 1, 2, 4, 16, 22, 28, 51-74, 91, 102-107, 111, 251 2, 16, 22, 28, 51-74, 91 16, 22, 28, 91 72 Ge 1, 2, 4, 51-55, 91, 102-107, 111 2, 51-55, 91 91 73 Ge 1, 2, 4, 51-54, 91, 102-107, 111, 251-253 2, 51-54, 91 91 74 Ge 1, 2, 4, 51-55, 91, 102-107, 111, 251-253 2, 51-55, 91 91 76 Ge 1, 2, 4, 51, 52, 91, 102-107, 111, 251-253 2, 51, 52, 91 91 75 As 1, 2, 4, 51-63, 91, 102-107, 111, 251-253 2, 51-63, 91 91 74 Se 1, 2, 4, 91, 102-107, 111, 251-253 2, 91 91 76 Se 1, 2, 4, 51-54, 91, 102-107, 111, 251-253 2, 51-54, 91 91 77 Se 1, 2, 4, 51-60, 91, 102-107, 111, 251-253 2, 51-60, 91 91 78 Se 1, 2, 4, 51-59, 91, 102-107, 111, 251-253 2, 51-59, 91 91 79 Se 1, 2, 4, 16, 17, 22, 28, 32, 51-79, 91, 102-107, 251 2, 16, 17, 22, 28, 32, 51-79, 91 16, 17, 22, 28, 32, 91 80 Se 1, 2, 4, 51-58, 91, 102-107, 111, 251-253 2, 51-58, 91 91 82 Se 1, 2, 4, 51-53, 91, 102-107, 111, 251-253 2, 51-53, 91 91 79 Br 1, 2, 4, 51-61, 91, 102-107, 111, 251-253 2, 51-61, 91 91 81 Br 1, 2, 4, 51-54, 91, 102-107, 111, 251-253 2, 51-54, 91 91 78 Kr 1, 2, 4, 16, 51-53, 91, 102-107, 111, 251-253 2, 16, 51-53, 91 16, 91 80 Kr 1, 2, 4, 16, 51-56, 91, 102-107, 111, 251-253 2, 16, 51-56, 91 16, 91 82 Kr 1, 2, 4, 16, 51-59, 91, 102-107, 111, 251-253 2, 16, 51-59, 91 16, 91 30

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 83 Kr 1, 2, 4, 16, 17, 51-56, 91, 102-107, 111, 251-253 2, 16, 17, 51-56, 91 16, 17, 91 84 Kr 1, 2, 4, 16, 51-63, 91, 102-107, 111, 251-253 2, 16, 51-63, 91 16, 91 85 Kr 1, 2, 4, 51, 91, 102-107, 111 2, 51, 91 91 86 Kr 1, 2, 4, 16, 17, 51-64, 91, 102-107, 111, 251-253 2, 16, 17, 51-64, 91 16, 17, 91 85 Rb 1, 2, 4, 51-53, 91, 102-107, 111, 251-253 2, 51-53, 91 91 86 Rb 1, 2, 4, 51, 91, 102-107, 111 2, 51, 91 91 87 Rb 1, 2, 4, 51, 52, 91, 102-107, 111, 251-253 2, 51, 52, 91 91 84 Sr 1, 2, 4, 91, 102-107, 111 2, 91 91 86 Sr 1, 2, 4, 51-57, 91, 102-107, 111, 251-253 2, 51-57, 91 91 87 Sr 1, 2, 4, 51-57, 91, 102-107, 111, 251-253 2, 51-57, 91 91 88 Sr 1, 2, 4, 51-55, 91, 102-107, 111, 251-253 2, 51-55, 91 91 89 Sr 1, 2, 4, 51-62, 91, 102-107, 111 2, 51-62, 91 91 90 Sr 1, 2, 4, 51-54, 91, 102-107, 111 2, 51-54, 91 91 89 Y 1, 2, 4, 16, 22, 28, 51-62, 91, 102-107 2, 16, 22, 28, 51-62, 91 16, 22, 28, 91 90 Y 1, 2, 4, 51, 52, 91, 102-107, 111 2, 51, 52, 91 91 91 Y 1, 2, 4, 51-58, 91, 102, 104-107, 111 2, 51-58, 91 91 90 Zr 1, 2, 4, 16, 22, 28, 32, 51-57, 91, 102-107, 111, 251 2, 16, 22, 28, 32, 51-57, 91 16, 22, 28, 32, 91 91 Zr 1, 2, 4, 16, 17, 22, 28, 32, 51-64, 91, 102-107, 251 2, 16, 17, 22, 28, 32, 51-64, 91 16, 17, 22, 28, 32, 91 92 Zr 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-67, 91, 102-105, 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, 91 107, 251 51-67, 91 93 Zr 1, 2, 4, 16, 22, 28, 51-62, 91, 102-107, 111, 251, 252 2, 16, 22, 28, 51-62, 91 16, 22, 28, 91 94 Zr 1, 2, 4, 16, 17, 22, 28, 32, 51-64, 91, 102-105, 107, 2, 16, 17, 22, 28, 32, 51-64, 91 16, 17, 22, 28, 32, 91 251 Reactions with energy-angle distributions in MF=6 95 Zr 1, 2, 4, 16, 51-64, 91, 102-107, 111, 251, 252 2, 16, 51-64, 91 16, 91 96 Zr 1, 2, 4, 16, 17, 22, 28, 51-57, 91, 102-105, 107, 251 2, 16, 17, 22, 28, 51-57, 91 16, 17, 22, 28, 91 93 Nb 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-73, 91, 102-105, 107 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, 91 51-73, 91 92 Mo 1, 2, 4, 16, 22, 28, 51-66, 91, 102-107, 111, 203-207, 2, 51-66 16, 22, 28, 91, 203-207 251 31

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 105 Pd 1, 2, 4, 16, 51-91, 102-107, 111, 251, 252 2, 16, 51-91 16, 91 106 Pd 1, 2, 4, 16, 51-70, 91, 102-107, 111, 251, 252 2, 16, 51-70, 91 16, 91 107 Pd 1, 2, 4, 16, 51-67, 91, 102-107, 111, 251, 252 2, 16, 51-67, 91 16, 91 108 Pd 1, 2, 4, 16, 51-60, 91, 102-107, 111, 251, 252 2, 16, 51-60, 91 16, 91 110 Pd 1, 2, 4, 16, 51-60, 91, 102-107, 111, 251, 252 2, 16, 51-60, 91 16, 91 107 Ag 1, 2, 4, 16, 51-56, 91, 102-107, 111, 251-253 2, 16, 51-56, 91 16, 91 109 Ag 1, 2, 4, 16, 51-64, 91, 102-107, 111, 251, 252 2, 16, 51-64, 91 16, 91 111 Ag 1, 2, 4, 51-60, 91, 102-107, 111 2, 51-60, 91 91 106 Cd 1, 2, 4, 16, 22, 28, 32, 33, 51-55, 91, 102-107 2, 16, 22, 28, 32, 33, 51-55, 91 16, 22, 28, 32, 33, 91 108 Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-60, 91, 102-107 2, 16, 17, 22, 28, 32, 33, 51-60, 91 110 Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-64, 91, 102-107 2, 16, 17, 22, 28, 32, 33, 51-64, 91 111 Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-61, 91, 102-107 2, 16, 17, 22, 28, 32, 33, 51-61, 91 112 Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-58, 91, 102-107 2, 16, 17, 22, 28, 32, 33, 51-58, 91 113 Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-62, 91, 102-107 2, 16, 17, 22, 28, 32, 33, 51-62, 91 114 Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-60, 91, 102-107 2, 16, 17, 22, 28, 32, 33, 51-60, 91 16, 17, 22, 28, 32, 33, 91 16, 17, 22, 28, 32, 33, 91 16, 17, 22, 28, 32, 33, 91 16, 17, 22, 28, 32, 33, 91 16, 17, 22, 28, 32, 33, 91 16, 17, 22, 28, 32, 33, 91 115m Cd 1, 2, 4, 91, 102-107, 111 2, 91 91 116 Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-56, 91, 102-107 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, 91 51-56, 91 113 In 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-74, 91, 102-107, 251 2, 16, 17, 22, 28, 32, 33, 51-74, 91 115 In 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-63, 91, 102-105, 107, 251 2, 16, 17, 22, 28, 32, 33, 51-63, 91 16, 17, 22, 28, 32, 33, 91 16, 17, 22, 28, 32, 33, 91 112 Sn 1, 2, 4, 16, 17, 22, 28, 51-73, 91, 102-107, 111 2, 16, 17, 22, 28, 51-73, 91 16, 17, 22, 28, 91 114 Sn 1, 2, 4, 16, 17, 22, 28, 51-76, 91, 102-107 2, 16, 17, 22, 28, 51-76, 91 16, 17, 22, 28, 91 Reactions with energy-angle distributions in MF=6 33

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 115 Sn 1, 2, 4, 16, 17, 22, 28, 32, 51-66, 91, 102-107 2, 16, 17, 22, 28, 32, 51-66, 91 16, 17, 22, 28, 32, 91 116 Sn 1, 2, 4, 16, 17, 22, 28, 51-60, 91, 102-105, 107 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, 91 117 Sn 1, 2, 4, 16, 17, 22, 28, 32, 51-62, 91, 102-105, 107 2, 16, 17, 22, 28, 32, 51-62, 91 16, 17, 22, 28, 32, 91 118 Sn 1, 2, 4, 16, 17, 22, 28, 51-57, 91, 102-105, 107 2, 16, 17, 22, 28, 51-57, 91 16, 17, 22, 28, 91 119 Sn 1, 2, 4, 16, 17, 22, 28, 32, 51-70, 91, 102-105, 107 2, 16, 17, 22, 28, 32, 51-70, 91 16, 17, 22, 28, 32, 91 120 Sn 1, 2, 4, 16, 17, 22, 28, 51-66, 91, 102-105, 107 2, 16, 17, 22, 28, 51-66, 91 16, 17, 22, 28, 91 122 Sn 1, 2, 4, 16, 17, 22, 28, 51-59, 91, 102-105, 107 2, 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, 91 123 Sn 1, 2, 4, 51-59, 91, 102-107, 111 2, 51-59, 91 91 124 Sn 1, 2, 4, 16, 17, 22, 28, 51-70, 91, 102-105, 107 2, 16, 17, 22, 28, 51-70, 91 16, 17, 22, 28, 91 125 Sn 1, 2, 4, 51-53, 91, 102-107, 111 2, 51-53, 91 91 126 Sn 1, 2, 4, 51-60, 91, 102-107, 111 2, 51-60, 91 91 121 Sb 1, 2, 4, 16, 17, 22, 28, 51-63, 91, 102-105, 107, 251 2, 16, 17, 22, 28, 51-63, 91 16, 17, 22, 28, 91 123 Sb 1, 2, 4, 16, 17, 22, 28, 51-58, 91, 102-105, 107, 251 2, 16, 17, 22, 28, 51-58, 91 16, 17, 22, 28, 91 124 Sb 1, 2, 4, 51-58, 91, 102-105, 107, 111 2, 51-58, 91 91 125 Sb 1, 2, 4, 51-69, 91, 102-107, 111 2, 51-69, 91 91 126 Sb 1, 2, 4, 51-55, 91, 102-107, 111 2, 51-55, 91 91 120 Te 1, 2, 4, 91, 102-107, 111, 251-253 2, 91 91 122 Te 1, 2, 4, 51-54, 91, 102-107, 111, 251-253 2, 51-54, 91 91 123 Te 1, 2, 4, 51-58, 91, 102-107, 111, 251-253 2, 51-58, 91 91 124 Te 1, 2, 4, 51-61, 91, 102-107, 111, 251-253 2, 51-61, 91 91 125 Te 1, 2, 4, 51-56, 91, 102-107, 111, 251-253 2, 51-56, 91 91 126 Te 1, 2, 4, 51-63, 91, 102-107, 111, 251-253 2, 51-63, 91 91 127m Te 1, 2, 4, 91, 102 2, 91 91 128 Te 1, 2, 4, 51-59, 91, 102-107, 111, 251 2, 51-59, 91 91 129m Te 1, 2, 4, 91, 102-107, 111 2, 91 91 130 Te 1, 2, 4, 51-60, 91, 102-107, 111, 251-253 2, 51-60, 91 91 132 Te 1, 2, 4, 51-56, 91, 102-107, 111 2, 51-56, 91 91 127 I 1, 2, 4, 16, 51-62, 91, 102-107, 111, 251, 252 2, 16, 51-62, 91 16, 91 Reactions with energy-angle distributions in MF=6 34

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 129 I 1, 2, 4, 16, 17, 22, 28, 51-60, 91, 102, 103, 107, 251-253 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, 91 130 I 1, 2, 4, 91, 102-107, 111 2, 91 91 131 I 1, 2, 4, 51-54, 91, 102-107, 111 2, 51-54, 91 91 135 I 1, 2, 4, 91, 102 2, 91 91 124 Xe 1, 2, 4, 16, 17, 51-54, 91, 102-107, 111 2, 16, 17, 51-54, 91 16, 17, 91 126 Xe 1, 2, 4, 16, 17, 51-54, 91, 102-107, 111 2, 16, 17, 51-54, 91 16, 17, 91 128 Xe 1, 2, 4, 16, 17, 51-53, 91, 102-107, 111 2, 16, 17, 51-53, 91 16, 17, 91 129 Xe 1, 2, 4, 16, 17, 51-56, 91, 102-107, 111 2, 16, 17, 51-56, 91 16, 17, 91 130 Xe 1, 2, 4, 16, 17, 51-56, 91, 102-107, 111 2, 16, 17, 51-56, 91 16, 17, 91 131 Xe 1, 2, 4, 16, 17, 51-56, 91, 102-107, 111, 251-253 2, 16, 17, 51-56, 91 16, 17, 91 132 Xe 1, 2, 4, 16, 17, 51-54, 91, 102-107, 111, 251-253 2, 16, 17, 51-54, 91 16, 17, 91 133 Xe 1, 2, 4, 51, 91, 102-107, 111 2, 51, 91 91 134 Xe 1, 2, 4, 16, 17, 51-53, 91, 102-107, 111, 251-253 2, 16, 17, 51-53, 91, 16, 17, 91 135 Xe 1, 2, 4, 51, 91, 102 2, 51, 91, 91 136 Xe 1, 2, 4, 16, 17, 51-53, 91, 102-107, 111 2, 16, 17, 51-53, 91 16, 17, 91 133 Cs 1, 2, 4, 16, 51-55, 91, 102, 103, 107 2, 16, 51-55, 91 16, 91 134 Cs 1, 2, 4, 51-55, 91, 102-107, 111, 251-253 2, 51-55, 91 91 135 Cs 1, 2, 4, 16, 51-68, 91, 102-107, 111, 251, 252 2, 16, 51-68, 91 16, 91 136 Cs 1, 2, 4, 91, 102-107, 111, 251-253 2, 91 91 137 Cs 1, 2, 4, 16, 51-60, 91, 102-107, 111, 251, 252 2, 16, 51-60, 91 16, 91 130 Ba 1, 2, 4, 16, 17, 22, 28, 32, 51-57, 91, 102-107, 111 2, 16, 17, 22, 28, 32, 51-57, 91 16, 17, 22, 28, 32, 91 132 Ba 1, 2, 4, 16, 17, 22, 28, 51-60, 91, 102-107, 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, 91 134 Ba 1, 2, 4, 16, 17, 22, 28, 51-63, 91, 102-105, 107, 251 2, 16, 17, 22, 28, 51-63, 91 16, 17, 22, 28, 91 135 Ba 1, 2, 4, 16, 17, 22, 28, 32, 51-57, 91, 102-107, 251 2, 16, 17, 22, 28, 32, 51-57, 91 16, 17, 22, 28, 32, 91 136 Ba 1, 2, 4, 16, 17, 22, 28, 51-60, 91, 102-105, 107, 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, 91 137 Ba 1, 2, 4, 16, 17, 22, 28, 32, 51-58, 91, 102-105, 107, 2, 16, 17, 22, 28, 32, 51-58, 91 16, 17, 22, 28, 32, 91 251 138 Ba 1, 2, 4, 16, 17, 22, 28, 51-69, 91, 102-105, 107, 251 2, 16, 17, 22, 28, 51-69, 91 16, 17, 22, 28, 91 Reactions with energy-angle distributions in MF=6 35

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 140 Ba 1, 2, 4, 16, 17, 91, 102-107, 111, 251, 252 2, 16, 17, 91 16, 17, 91 138 La 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-65, 91, 102-107, 251 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, 91 51-65, 91 139 La 1, 2, 4, 16, 51-73, 91, 102-107, 111, 251, 252 2, 16, 51-73, 91 16, 91 140 La 1, 2, 4, 51-56, 91, 102, 104-107, 111 2, 51-56, 91 91 140 Ce 1, 2, 4, 51-58, 91, 102-107, 111 2, 51-58, 91 91 141 Ce 1, 2, 4, 16, 51-62, 91, 102-107, 111, 251, 252 2, 16, 51-62, 91 16, 91 142 Ce 1, 2, 4, 16, 17, 51-56, 91, 102-107, 111, 251, 252 2, 16, 17, 51-56, 91 16, 17, 91 143 Ce 1, 2, 4, 91, 102-107, 111 2, 91 91 144 Ce 1, 2, 4, 16, 17, 51-68, 91, 102-107, 111, 251, 252 2, 16, 17, 51-68, 91 16, 17, 91 141 Pr 1, 2, 4, 16, 51-74, 91, 102-107, 111, 251, 252 2, 16, 51-74, 91 16, 91 142 Pr 1, 2, 4, 91, 102-107, 111 2, 91 91 143 Pr 1, 2, 4, 51-56, 91, 102-107, 111 2, 51-56, 91 91 142 Nd 1, 2, 4, 51-58, 91, 102-107, 111, 251-253 2, 51-58, 91 91 143 Nd 1, 2, 4, 16, 51-76, 91, 102-107, 111, 251, 252 2, 16, 51-76, 91 16, 91 144 Nd 1, 2, 4, 16, 51-64, 91, 102-107, 111, 251, 252 2, 16, 51-64, 91 16, 91 145 Nd 1, 2, 4, 16, 51-64, 91, 102-107, 111, 251, 252 2, 16, 51-64, 91 16, 91 146 Nd 1, 2, 4, 16, 51-63, 91, 102-107, 111, 251, 252 2, 16, 51-63, 91 16, 91 147 Nd 1, 2, 4, 51-53, 91, 102-107, 111, 251-253 2, 51-53, 91 91 148 Nd 1, 2, 4, 16, 51-57, 91, 102-107, 111, 251, 252 2, 16, 51-57, 91 16, 91 150 Nd 1, 2, 4, 16, 17, 22, 28, 51-59, 91, 102-107, 111, 251-253 2, 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, 91 147 Pm 1, 2, 4, 16, 51-61, 91, 102-107, 111, 251, 252 2, 16, 51-61, 91 16, 91 148 Pm 1, 2, 4, 91, 102 2, 91 91 148m Pm 1, 2, 4, 91, 102, 251-253 2, 91 91 149 Pm 1, 2, 4, 51-56, 91, 102-107, 111 2, 51-56, 91 91 151 Pm 1, 2, 4, 51-56, 91, 102-107, 111 2, 51-56, 91 91 144 Sm 1, 2, 4, 91, 102-107, 111, 251-253 2, 91 91 147 Sm 1, 2, 4, 16, 51-64, 91, 102-107, 111, 251, 252 2, 16, 51-64, 91 16, 91 Reactions with energy-angle distributions in MF=6 36

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 148 Sm 1, 2, 4, 51-66, 91, 102-107, 111 2, 51-66, 91 91 149 Sm 1, 2, 4, 16, 17, 51-60, 91, 102, 103, 107 2, 16, 17, 51-60, 91 16, 17, 91 150 Sm 1, 2, 4, 51-66, 91, 102-107, 111, 251-253 2, 51-66, 91 91 151 Sm 1, 2, 4, 16, 51-91, 102-107, 111, 251, 252 2, 16, 51-91 16, 91 152 Sm 1, 2, 4, 16, 51-63, 91, 102-107, 111, 251, 252 2, 16, 51-63, 91 16, 91 153 Sm 1, 2, 4, 51-62, 91, 102-107, 111 2, 51-62, 91 91 154 Sm 1, 2, 4, 51-69, 91, 102-107, 111, 251-253 2, 51-69, 91 91 151 Eu 1, 2, 4, 16, 17, 22, 28, 51-59, 91, 102-107, 111 2, 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, 91 152 Eu 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-61, 91, 102-107, 251 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, 91 51-61, 91 153 Eu 1, 2, 4, 16, 17, 22, 28, 51-61, 91, 102, 103, 107, 251 2, 16, 17, 22, 28, 51-61, 91 16, 17, 22, 28, 91 154 Eu 1, 2, 4, 16, 17, 22, 28, 51-55, 91, 102-107 2, 16, 17, 22, 28, 51-55, 91 16, 17, 22, 28, 91 155 Eu 1, 2, 4, 16, 17, 22, 28, 51-59, 91, 102-107 2, 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, 91 156 Eu 1, 2, 4, 51-55, 91, 102-107, 111 2, 51-55, 91 91 157 Eu 1, 2, 4, 91, 102 2, 91 91 152 Gd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-79, 91, 102-107, 251 2, 16, 17, 22, 28, 32, 33, 51-79, 91 154 Gd 1, 2, 4, 51-65, 91, 102-107, 111 2, 51-65, 91 91 155 Gd 1, 2, 4, 51-79, 91, 102-107, 111, 251 2, 51-79, 91 91 156 Gd 1, 2, 4, 16, 51-64, 91, 102-107, 111 2, 16, 51-64, 91 16, 91 157 Gd 1, 2, 4, 51-78, 91, 102-107, 111, 251 2, 51-78, 91 91 158 Gd 1, 2, 4, 51-61, 91, 102-107, 111 2, 51-61, 91 91 160 Gd 1, 2, 4, 51-56, 91, 102-105, 107 2, 51-56, 91 91 159 Tb 1, 2, 4, 16, 51-66, 91, 102, 251, 252 2, 16, 51-66, 91 16, 91 160 Tb 1, 2, 4, 91, 102, 251-253 2, 91 91 160 Dy 1, 2, 4, 51-64, 91, 102, 251-253 2, 51-64, 91 91 161 Dy 1, 2, 4, 51-57, 91, 102, 251-253 2, 51-57, 91 91 162 Dy 1, 2, 4, 51-56, 91, 102, 251-253 2, 51-56, 91 91 163 Dy 1, 2, 4, 51-56, 91, 102, 251-253 2, 51-56, 91 91 16, 17, 22, 28, 32, 33, 91 Reactions with energy-angle distributions in MF=6 37

Table 2. List of reactions for which cross-sections, angular, energy and energy-angle distributions are available in the JEFF-3.0 library (cont.) Nuclide Reactions described in MF=3 Reactions with angular distributions in MF=4 Reactions with energy distributions in MF=5 Reactions with energy-angle distributions in MF=6 164 Dy 1, 2, 4, 16, 17, 51-62, 91, 102, 103, 107, 251-253 2, 16, 17, 51-62, 91 16, 17, 91 165 Ho 1, 2, 4, 16, 17, 37, 51-63, 91, 102 2, 16, 17, 37, 51-63, 91 16, 17, 37, 91 162 Er 1, 2, 4, 16, 17, 28, 51-58, 91, 102, 103, 107, 251-253 2, 16, 17, 28, 51-58, 91 16, 17, 28, 91 164 Er 1, 2, 4, 16, 17, 28, 51-60, 91, 102, 103, 107, 251-253 2, 16, 17, 28, 51-60, 91 16, 17, 28, 91 166 Er 1, 2, 4, 16, 17, 51-57, 91, 102, 103, 107, 251-253 2, 16, 17, 51-57, 91 16, 17, 91 167 Er 1, 2, 4, 16, 17, 28, 51-57, 91, 102, 103, 107, 251-253 2, 16, 17, 28, 51-57, 91 16, 17, 28, 91 168 Er 1, 2, 4, 16, 17, 28, 51-59, 91, 102, 103, 107, 251-253 2, 16, 17, 28, 51-59, 91 16, 17, 28, 91 170 Er 1, 2, 4, 16, 17, 28, 51-57, 91, 102, 103, 107, 251-253 2, 16, 17, 28, 51-57, 91 16, 17, 28, 91 175 Lu 1, 2, 4, 16, 17, 51-58, 91, 102, 103, 107, 251-253 2, 16, 17, 51-58, 91 16, 17, 91 176 Lu 1, 2, 4, 16, 17, 51-58, 91, 102, 103, 107, 251-253 2, 16, 17, 51-58, 91 16, 17, 91 174 Hf 1, 2, 4, 16, 17, 51-68, 91, 102, 251 2, 16, 17, 51-68, 91 16, 17, 91 176 Hf 1, 2, 4, 16, 17, 51-73, 91, 102, 103, 107, 251 2, 16, 17, 51-73, 91 16, 17, 91 177 Hf 1, 2, 4, 16, 17, 51-66, 91, 102, 103, 107, 251 2, 16, 17, 51-66, 91 16, 17, 91 178 Hf 1, 2, 4, 16, 17, 51-71, 91, 102, 103, 107, 251 2, 16, 17, 51-71, 91 16, 17, 91 179 Hf 1, 2, 4, 16, 17, 51-62, 91, 102, 103, 107, 251 2, 16, 17, 51-62, 91 16, 17, 91 180 Hf 1, 2, 4, 16, 17, 51-61, 91, 102, 103, 107, 251 2, 16, 17, 51-61, 91 16, 17, 91 181 Ta 1, 2, 4, 16, 17, 28, 51-64, 91, 102, 103, 107, 251 2, 16, 17, 28, 51-64, 91 16, 17, 28, 91 182 Ta1 1, 2, 4, 16, 17, 51-58, 91, 102, 107, 251-253 2, 16, 17, 51-58, 91 16, 17, 91 182 W 1, 2, 4, 16, 17, 22, 28, 51-70, 91, 102-104, 107, 251 2, 16, 17, 22, 28, 51-70, 91 16, 17, 22, 28, 91 183 W 1, 2, 4, 16, 17, 22, 28, 51-60, 91, 102-104, 107, 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, 91 184 W 1, 2, 4, 16, 17, 22, 28, 51-60, 91, 102-104, 107, 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, 91 186 W 1, 2, 4, 16, 17, 22, 28, 51-62, 91, 102-104, 107, 251 2, 16, 17, 22, 28, 51-62, 91 16, 17, 22, 28, 91 185 Re 1, 2, 4, 16, 17, 51-59, 91, 102 2, 16, 17, 51-59, 91 16, 17, 91 187 Re 1, 2, 4, 16, 17, 51-66, 91, 102 2, 16, 17, 51-66, 91 16, 17, 91 nat Os 1, 2, 4, 16, 17, 51-67, 91, 102, 103, 107, 251-253 2, 16, 17, 51-67, 91 16, 17, 91 nat Ir 1, 2, 4, 16, 17, 51-58, 91, 102, 103, 107, 251-253 2, 16, 17, 51-58, 91 16, 17, 91 nat Pt 1, 2, 4, 16, 17, 91, 102, 251-253 2 16, 17, 91 197 Au 1, 2, 4, 16, 17, 37, 51-63, 91, 102, 103, 107 2, 16, 17, 37, 51-63, 91 16, 17, 37, 91 nat Hg 1-4, 16, 17, 22, 28, 51-80, 91, 102-105, 107 2, 51-80, 16, 17, 22, 28, 91 38