The JEFF-3.0 Nuclear Data Library

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

2 ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 30 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. The OECD member countries are: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Korea, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities takes part in the work of the OECD. OECD Publishing disseminates widely the results of the Organisation s statistics gathering and research on economic, social and environmental issues, as well as the conventions, guidelines and standards agreed by its members. * * * This work is published on the responsibility of the Secretary-General of the OECD. The opinions expressed and arguments employed herein do not necessarily reflect the official views of the Organisation or of the governments of its member countries. NUCLEAR ENERGY AGENCY The OECD Nuclear Energy Agency (NEA) was established on 1 st February 1958 under the name of the OEEC European Nuclear Energy Agency. It received its present designation on 20 th April 1972, when Japan became its first non-european full member. NEA membership today consists of 28 OECD member countries: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Luxembourg, Mexico, the Netherlands, Norway, Portugal, Republic of Korea, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities also takes part in the work of the Agency. The mission of the NEA is: to assist its member countries in maintaining and further developing, through international co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes, as well as to provide authoritative assessments and to forge common understandings on key issues, as input to government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy and sustainable development. Specific areas of competence of the NEA include safety and regulation of nuclear activities, radioactive waste management, radiological protection, nuclear science, economic and technical analyses of the nuclear fuel cycle, nuclear law and liability, and public information. The NEA Data Bank provides nuclear data and computer program services for participating countries. In these and related tasks, the NEA works in close collaboration with the International Atomic Energy Agency in Vienna, with which it has a Co-operation Agreement, as well as with other international organisations in the nuclear field. OECD 2005 No reproduction, copy, transmission or translation of this publication may be made without written permission. Applications should be sent to OECD Publishing: rights@oecd.org or by fax (+33-1) Permission to photocopy a portion of this work should be addressed to the Centre Français d exploitation du droit de Copie, 20 rue des Grands-Augustins, Paris, France (contact@cfcopies.com).

3 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

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5 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 Figures Tables Annex Annex

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7 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

8 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

9 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 The temperature used was 293 K and E 0 = 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: Refs. [12-14] provide more details as concerns this feedback. 9

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11 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

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13 FIGURES 13

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

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17 TABLES 17

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19 Table 1. List of materials in the JEFF-3.0 library Nuclide or element MAT and isomeric state number Evaluation file 1-H JEFF30N125_1.ASC 1-H JEFF30N128_1.ASC 1-H JEFF30N131_1.ASC 2-He JEFF30N225_1.ASC 2-He JEFF30N228_1.ASC 3-Li JEFF30N325_1.ASC 3-Li JEFF30N328_1.ASC 4-Be JEFF30N425_2.ASC 5-B JEFF30N525_1.ASC 5-B JEFF30N528_1.ASC 6-C-nat 600 JEFF30N600_1.ASC 7-N JEFF30N725_2.ASC 7-N JEFF30N728_2.ASC 8-O JEFF30N825_1.ASC 8-O JEFF30N828_1.ASC 9-F JEFF30N925_1.ASC 11-Na JEFF30N1122_1.ASC 11-Na JEFF30N1125_2.ASC 12-Mg-nat 1200 JEFF30N1200_1.ASC 13-Al JEFF30N1325_2.ASC 14-Si JEFF30N1425_4.ASC 14-Si JEFF30N1428_2.ASC 14-Si JEFF30N1431_2.ASC 15-P JEFF30N1525_1.ASC 16-S-nat 1600 JEFF30N1600_2.ASC 17-Cl-nat 1700 JEFF30N1700_1.ASC 18-Ar JEFF30N1825_1.ASC 18-Ar JEFF30N1831_1.ASC 18-Ar JEFF30N1837_1.ASC 19-K-nat 1900 JEFF30N1900_2.ASC 20-Ca-nat 2000 JEFF30N2000_2.ASC 21-Sc JEFF30N2125_1.ASC 22-Ti-nat 2200 JEFF30N2200_1.ASC 23-V-nat 2300 JEFF30N2300_1.ASC 24-Cr JEFF30N2425_1.ASC 24-Cr JEFF30N2431_1.ASC 24-Cr JEFF30N2434_3.ASC 24-Cr JEFF30N2437_3.ASC 25-Mn JEFF30N2525_1.ASC 26-Fe JEFF30N2625_1.ASC 26-Fe JEFF30N2631_2.ASC 19

20 Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 26-Fe JEFF30N2634_1.ASC 26-Fe JEFF30N2637_1.ASC 27-Co JEFF30N2722_3.ASC 27-Co-58m 2723 JEFF30N2723_2.ASC 27-Co JEFF30N2725_1.ASC 28-Ni JEFF30N2825_2.ASC 28-Ni JEFF30N2828_1.ASC 28-Ni JEFF30N2831_2.ASC 28-Ni JEFF30N2834_1.ASC 28-Ni JEFF30N2837_1.ASC 28-Ni JEFF30N2843_1.ASC 29-Cu JEFF30N2925_1.ASC 29-Cu JEFF30N2931_1.ASC 30-Zn-nat 3000 JEFF30N3000_1.ASC 31-Ga-nat 3100 JEFF30N3100_1.ASC 32-Ge JEFF30N3225_1.ASC 32-Ge JEFF30N3231_1.ASC 32-Ge JEFF30N3234_1.ASC 32-Ge JEFF30N3237_1.ASC 32-Ge JEFF30N3243_1.ASC 33-As JEFF30N3325_1.ASC 34-Se JEFF30N3425_1.ASC 34-Se JEFF30N3431_2.ASC 34-Se JEFF30N3434_1.ASC 34-Se JEFF30N3437_1.ASC 34-Se JEFF30N3440_1.ASC 34-Se JEFF30N3443_1.ASC 34-Se JEFF30N3449_1.ASC 35-Br JEFF30N3525_1.ASC 35-Br JEFF30N3531_1.ASC 36-Kr JEFF30N3625_1.ASC 36-Kr JEFF30N3631_1.ASC 36-Kr JEFF30N3637_1.ASC 36-Kr JEFF30N3640_1.ASC 36-Kr JEFF30N3643_1.ASC 36-Kr JEFF30N3646_1.ASC 36-Kr JEFF30N3649_1.ASC 37-Rb JEFF30N3725_1.ASC 37-Rb JEFF30N3728_1.ASC 37-Rb JEFF30N3731_1.ASC 38-Sr JEFF30N3825_1.ASC 20

21 Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 38-Sr JEFF30N3831_1.ASC 38-Sr JEFF30N3834_1.ASC 38-Sr JEFF30N3837_1.ASC 38-Sr JEFF30N3840_1.ASC 38-Sr JEFF30N3843_1.ASC 39-Y JEFF30N3925_1.ASC 39-Y JEFF30N3928_1.ASC 39-Y JEFF30N3931_1.ASC 40-Zr JEFF30N4025_1.ASC 40-Zr JEFF30N4028_1.ASC 40-Zr JEFF30N4031_1.ASC 40-Zr JEFF30N4034_2.ASC 40-Zr JEFF30N4037_1.ASC 40-Zr JEFF30N4040_1.ASC 40-Zr JEFF30N4043_1.ASC 41-Nb JEFF30N4125_1.ASC 42-Mo JEFF30N4225_2.ASC 42-Mo JEFF30N4231_2.ASC 42-Mo JEFF30N4234_2.ASC 42-Mo JEFF30N4237_2.ASC 42-Mo JEFF30N4240_2.ASC 42-Mo JEFF30N4243_2.ASC 42-Mo JEFF30N4246_1.ASC 42-Mo JEFF30N4249_2.ASC 43-Tc JEFF30N4331_1.ASC 44-Ru JEFF30N4425_1.ASC 44-Ru JEFF30N4431_1.ASC 44-Ru JEFF30N4434_1.ASC 44-Ru JEFF30N4437_1.ASC 44-Ru JEFF30N4440_1.ASC 44-Ru JEFF30N4443_1.ASC 44-Ru JEFF30N4446_1.ASC 44-Ru JEFF30N4449_1.ASC 44-Ru JEFF30N4452_1.ASC 44-Ru JEFF30N4455_1.ASC 45-Rh JEFF30N4525_2.ASC 45-Rh JEFF30N4531_1.ASC 46-Pd JEFF30N4625_1.ASC 46-Pd JEFF30N4631_1.ASC 46-Pd JEFF30N4634_1.ASC 46-Pd JEFF30N4637_1.ASC 21

22 Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 46-Pd JEFF30N4640_1.ASC 46-Pd JEFF30N4643_1.ASC 46-Pd JEFF30N4649_1.ASC 47-Ag JEFF30N4725_1.ASC 47-Ag JEFF30N4731_1.ASC 47-Ag JEFF30N4737_1.ASC 48-Cd JEFF30N4825_1.ASC 48-Cd JEFF30N4831_1.ASC 48-Cd JEFF30N4837_1.ASC 48-Cd JEFF30N4840_1.ASC 48-Cd JEFF30N4843_1.ASC 48-Cd JEFF30N4846_1.ASC 48-Cd JEFF30N4849_1.ASC 48-Cd-115m 4853 JEFF30N4853_1.ASC 48-Cd JEFF30N4855_1.ASC 49-In JEFF30N4925_1.ASC 49-In JEFF30N4931_1.ASC 50-Sn JEFF30N5025_1.ASC 50-Sn JEFF30N5031_1.ASC 50-Sn JEFF30N5034_1.ASC 50-Sn JEFF30N5037_1.ASC 50-Sn JEFF30N5040_1.ASC 50-Sn JEFF30N5043_1.ASC 50-Sn JEFF30N5046_1.ASC 50-Sn JEFF30N5049_1.ASC 50-Sn JEFF30N5055_1.ASC 50-Sn JEFF30N5058_1.ASC 50-Sn JEFF30N5061_1.ASC 50-Sn JEFF30N5064_1.ASC 50-Sn JEFF30N5067_1.ASC 51-Sb JEFF30N5125_2.ASC 51-Sb JEFF30N5131_2.ASC 51-Sb JEFF30N5134_1.ASC 51-Sb JEFF30N5137_1.ASC 51-Sb JEFF30N5140_1.ASC 52-Te JEFF30N5225_1.ASC 52-Te JEFF30N5231_1.ASC 52-Te JEFF30N5234_1.ASC 52-Te JEFF30N5237_1.ASC 52-Te JEFF30N5240_1.ASC 52-Te JEFF30N5243_1.ASC 22

23 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 JEFF30N5249_1.ASC 52-Te-129m 5253 JEFF30N5253_1.ASC 52-Te JEFF30N5255_1.ASC 52-Te JEFF30N5261_1.ASC 53-I JEFF30N5325_1.ASC 53-I JEFF30N5331_1.ASC 53-I JEFF30N5334_1.ASC 53-I JEFF30N5337_1.ASC 53-I JEFF30N5349_1.ASC 54-Xe JEFF30N5425_1.ASC 54-Xe JEFF30N5431_1.ASC 54-Xe JEFF30N5437_1.ASC 54-Xe JEFF30N5440_1.ASC 54-Xe JEFF30N5443_1.ASC 54-Xe JEFF30N5446_1.ASC 54-Xe JEFF30N5449_1.ASC 54-Xe JEFF30N5452_1.ASC 54-Xe JEFF30N5455_1.ASC 54-Xe JEFF30N5458_1.ASC 54-Xe JEFF30N5461_1.ASC 55-Cs JEFF30N5525_2.ASC 55-Cs JEFF30N5528_1.ASC 55-Cs JEFF30N5531_1.ASC 55-Cs JEFF30N5534_1.ASC 55-Cs JEFF30N5537_1.ASC 56-Ba JEFF30N5625_1.ASC 56-Ba JEFF30N5631_1.ASC 56-Ba JEFF30N5637_1.ASC 56-Ba JEFF30N5640_1.ASC 56-Ba JEFF30N5643_1.ASC 56-Ba JEFF30N5646_1.ASC 56-Ba JEFF30N5649_1.ASC 56-Ba JEFF30N5655_1.ASC 57-La JEFF30N5725_1.ASC 57-La JEFF30N5728_1.ASC 57-La JEFF30N5731_1.ASC 58-Ce JEFF30N5837_1.ASC 58-Ce JEFF30N5840_1.ASC 58-Ce JEFF30N5843_1.ASC 58-Ce JEFF30N5846_1.ASC 23

24 Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 58-Ce JEFF30N5849_1.ASC 59-Pr JEFF30N5925_1.ASC 59-Pr JEFF30N5928_1.ASC 59-Pr JEFF30N5931_1.ASC 60-Nd JEFF30N6025_1.ASC 60-Nd JEFF30N6028_2.ASC 60-Nd JEFF30N6031_1.ASC 60-Nd JEFF30N6034_1.ASC 60-Nd JEFF30N6037_1.ASC 60-Nd JEFF30N6040_1.ASC 60-Nd JEFF30N6043_1.ASC 60-Nd JEFF30N6049_1.ASC 61-Pm JEFF30N6149_2.ASC 61-Pm JEFF30N6152_1.ASC 61-Pm-148m 6153 JEFF30N6153_1.ASC 61-Pm JEFF30N6155_1.ASC 61-Pm JEFF30N6161_1.ASC 62-Sm JEFF30N6225_1.ASC 62-Sm JEFF30N6234_1.ASC 62-Sm JEFF30N6237_1.ASC 62-Sm JEFF30N6240_2.ASC 62-Sm JEFF30N6243_1.ASC 62-Sm JEFF30N6246_1.ASC 62-Sm JEFF30N6249_1.ASC 62-Sm JEFF30N6252_1.ASC 62-Sm JEFF30N6255_1.ASC 63-Eu JEFF30N6325_2.ASC 63-Eu JEFF30N6328_2.ASC 63-Eu JEFF30N6331_2.ASC 63-Eu JEFF30N6334_2.ASC 63-Eu JEFF30N6337_2.ASC 63-Eu JEFF30N6340_1.ASC 63-Eu JEFF30N6343_1.ASC 64-Gd JEFF30N6425_1.ASC 64-Gd JEFF30N6431_1.ASC 64-Gd JEFF30N6434_1.ASC 64-Gd JEFF30N6437_1.ASC 64-Gd JEFF30N6440_1.ASC 64-Gd JEFF30N6443_1.ASC 64-Gd JEFF30N6449_1.ASC 65-Tb JEFF30N6525_1.ASC 24

25 Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 65-Tb JEFF30N6528_1.ASC 66-Dy JEFF30N6637_1.ASC 66-Dy JEFF30N6640_1.ASC 66-Dy JEFF30N6643_1.ASC 66-Dy JEFF30N6646_1.ASC 66-Dy JEFF30N6649_1.ASC 67-Ho JEFF30N6725_1.ASC 68-Er JEFF30N6825_2.ASC 68-Er JEFF30N6831_1.ASC 68-Er JEFF30N6837_1.ASC 68-Er JEFF30N6840_1.ASC 68-Er JEFF30N6843_2.ASC 68-Er JEFF30N6846_1.ASC 71-Lu JEFF30N7125_1.ASC 71-Lu JEFF30N7128_1.ASC 72-Hf JEFF30N7225_1.ASC 72-Hf JEFF30N7231_1.ASC 72-Hf JEFF30N7234_1.ASC 72-Hf JEFF30N7237_1.ASC 72-Hf JEFF30N7240_1.ASC 72-Hf JEFF30N7243_2.ASC 73-Ta JEFF30N7328_1.ASC 73-Ta JEFF30N7331_2.ASC 74-W JEFF30N7431_2.ASC 74-W JEFF30N7434_2.ASC 74-W JEFF30N7437_2.ASC 74-W JEFF30N7443_2.ASC 75-Re JEFF30N7525_1.ASC 75-Re 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 JEFF30N7925_1.ASC 80-Hg-nat 8000 JEFF30N8000_2.ASC 81-Tl-nat 8100 JEFF30N8100_2.ASC 82-Pb JEFF30N8225_2.ASC 82-Pb JEFF30N8231_3.ASC 82-Pb JEFF30N8234_3.ASC 82-Pb JEFF30N8237_3.ASC 83-Bi JEFF30N8325_1.ASC 90-Th JEFF30N9025_2.ASC 25

26 Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 90-Th JEFF30N9028_2.ASC 90-Th JEFF30N9031_2.ASC 90-Th JEFF30N9034_2.ASC 90-Th JEFF30N9040_2.ASC 90-Th JEFF30N9043_2.ASC 90-Th JEFF30N9046_2.ASC 91-Pa JEFF30N9131_1.ASC 91-Pa JEFF30N9137_2.ASC 92-U JEFF30N9219_1.ASC 92-U JEFF30N9222_2.ASC 92-U JEFF30N9225_1.ASC 92-U JEFF30N9228_3.ASC 92-U JEFF30N9231_1.ASC 92-U JEFF30N9234_2.ASC 92-U JEFF30N9237_4.ASC 93-Np JEFF30N9343_1.ASC 93-Np JEFF30N9346_2.ASC 93-Np JEFF30N9349_1.ASC 93-Np JEFF30N9352_2.ASC 94-Pu JEFF30N9428_2.ASC 94-Pu JEFF30N9431_2.ASC 94-Pu JEFF30N9434_3.ASC 94-Pu JEFF30N9437_3.ASC 94-Pu JEFF30N9440_3.ASC 94-Pu JEFF30N9443_3.ASC 94-Pu JEFF30N9446_2.ASC 94-Pu JEFF30N9449_1.ASC 94-Pu JEFF30N9452_2.ASC 95-Am JEFF30N9543_2.ASC 95-Am JEFF30N9546_3.ASC 95-Am-242m 9547 JEFF30N9547_2.ASC 95-Am JEFF30N9549_2.ASC 95-Am JEFF30N9552_1.ASC 95-Am-244m 9553 JEFF30N9553_1.ASC 96-Cm JEFF30N9628_2.ASC 96-Cm JEFF30N9631_2.ASC 96-Cm JEFF30N9634_2.ASC 96-Cm JEFF30N9637_2.ASC 96-Cm JEFF30N9640_1.ASC 96-Cm JEFF30N9643_1.ASC 96-Cm JEFF30N9646_2.ASC 26

27 Table 1. List of materials in the JEFF-3.0 library (cont.) Nuclide or element MAT and isomeric state number Evaluation file 96-Cm JEFF30N9649_3.ASC 96-Cm JEFF30N9652_1.ASC 96-Cm JEFF30N9655_1.ASC 97-Bk JEFF30N9752_2.ASC 97-Bk JEFF30N9755_2.ASC 98-Cf JEFF30N9852_2.ASC 98-Cf JEFF30N9855_1.ASC 98-Cf JEFF30N9858_1.ASC 98-Cf JEFF30N9861_2.ASC 98-Cf JEFF30N9867_1.ASC 99-Es JEFF30N9914_2.ASC 99-Es 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

28 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, H 1, 2, 16, H 1, 2, 16, 17 2, He 1, 2, He 1, 2, Li 1, 2, 4, 24, 51-81, 102, 103, 105 2, 24, 51-81, 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, , 107, , 107, B 1, 2, 4, 51-85, , 107, 113, , 800, 801 2, B 1, 2, 4, 16, 22, 28, 51-60, 91, 102, 103, 105, 107 2, , 22, 28, 91, 103, , 24, 28, 32, 33, 41, 91, nat C 1-4, 16, 24, 28, 32, 33, 41, 51-73, 91, , 107, 111, 112, 115, 116, , N 1, 2, 4, 16, 51-90, , 107, 108, , , 700, 701, , 16, 24, 28, 32, 33, 41, 51-73, 91 2, N 1, 2, 4, 16, 22, 28, 51-57, 91, , 107 2, 16, 22, 28, 51-57, 91 16, 22, 28, O 1, 2, 4, 51-88, , 107, , O 1, 2, 4, 16, 22, 28, 51-62, 91, , 107 2, 16, 22, 28, 51-62, 91 16, 22, 28, F 1-4, 16, 22, 28, 51-71, 91, , 107 2, , 22, 28, 91, 102, 103, Na 1, 2, 4, 16, 22, 28, 51-61, 91, , 107, 108, 251 2, 16, 22, 28, 51-61, 91 16, 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, , 22, 28, Al 1-5, 16, 22, 28, 32, 33, 45, 51-89, 91, , 107, 108, 111, 112, 117, , , , 749, , Si 1-4, 16, 22, 28, 51-67, 91, , 111, , 649, , 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, 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, P 1, 2, 4, 16, 22, 28, 51-56, 91, 102, 103, 107, 251 2, 16, 22, 28, 51-56, 91 16, 22, 28, , 16, 22, 28, 32, 33, 45, 51-89, 91, 108, 111, 112, 117, , , , 749, , , 22, 28, 51-67, 91, , 649, ,

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 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, , 16, 22, 28, 51-63, 91 16, 22, 28, Ar 1, 2, 4, 16, 22, 28, 51-71, 91, , 107, 108, 251, 2, 16, 22, 28, 51-71, 91 16, Ar 1, 2, 4, 16, 22, 28, 51-69, 91, , 107, 108, 251, 2, 16, 22, 28, 51-69, 91 16, Ar 1, 2, 4, 16, 17, 22, 28, 51-71, 91, , 107, 251, 2, 16, 17, 22, 28, 51-71, 91 16, 17, 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, Reactions with energy-angle distributions in MF=6 45 Sc 1, 2, 4, 16, 22, 28, 51-64, 91, , 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, , 111, 112 2, 32, , 22, 28, 91, 103, Cr 1-4, 16, 22, 28, 51-56, 91, , , 22, 28, 51-56, 91, 103, Cr 1-5, 51-66, 102, , , 51-66, , Cr 1-4, 16, 22, 28, 51-63, 91, 102, 103, , 22, 28, 51-63, 91, 103, Cr 1-4, 16, 51-54, 91, 102, 103, , 51-54, 91, 103, Mn 1-4, 16, 22, 28, 51-66, 91, , , 251 2, , 22, 28, 91, Fe 1-4, 16, 22, 28, 51-57, 91, , , 22, 28, 51-57, 91, 103, Fe 1-4, 16, 22, 28, 51-82, 91, , , 649, 2, 51-82, , , 22, 28, 91, 649, , Fe 1, 2, 4, 16, 22, 28, 51-65, 91, , 107, 251 2, 16, 22, 28, 51-65, 91 16, 22, 28, Fe 1, 2, 4, 16, 22, 28, 51-67, 91, , 107, 251 2, 16, 22, 28, 51-67, 91 16, 22, 28, Co 1, 2, 4, 16, 22, 28, 51-62, 91, , 107, 251 2, 16, 22, 28, 51-62, 91 16, 91 58m Co 1, 2, 4, 16, 22, 28, 51-62, 91, , 107, 251 2, 16, 22, 28, 51-62, 91 16, Co 1, 2, 4, 16, 22, 28, 32, 33, 51-69, 91, , 111, 2, 16, 22, 28, 32, 33, 51-69, 91 16, 22, 28, 32, 33, Ni 1-4, 16, 22, 28, 51-58, 91, , , 22, 28, 51-58, 91, 103,

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 Reactions with energy-angle distributions in MF=6 59 Ni 1-3, 16, 22, 28, 32, 34, , 111 2, 16, 22, 28, 32, Ni 1-4, 16, 22, 28, 51-61, 91, , 22, 28, 51-61, 91, 103, Ni 1-4, 16, 28, 51-58, 91, 102, 103, 107, , 28, 51-58, 91, 103, Ni 1-4, 16, 22, 28, 51-54, 91, , , 22, 28, 51-54, 91, 103, Ni 1-4, 16, 22, 28, 51, 52, 91, , , 22, 28, 51, 52, 91, 103, Cu 1-4, 16, 22, 28, 51-72, 91, , 106, , 22, 28, 51-72, 91, 103, Cu 1-4, 16, 22, 28, 51-63, 91, , 22, 28, 51-63, 91, 103, 107 nat Zn 1, 2, 4, 16, 17, 22, 28, 51, 91, 102, 103, 105, 107, nat Ga 1, 2, 4, 16, 17, 22, 28, 32, 51-88, 91, , 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, Ge 1, 2, 4, 16, 22, 28, 51-74, 91, , 111, 251 2, 16, 22, 28, 51-74, 91 16, 22, 28, Ge 1, 2, 4, 51-55, 91, , 111 2, 51-55, Ge 1, 2, 4, 51-54, 91, , 111, , 51-54, Ge 1, 2, 4, 51-55, 91, , 111, , 51-55, Ge 1, 2, 4, 51, 52, 91, , 111, , 51, 52, As 1, 2, 4, 51-63, 91, , 111, , 51-63, Se 1, 2, 4, 91, , 111, , Se 1, 2, 4, 51-54, 91, , 111, , 51-54, Se 1, 2, 4, 51-60, 91, , 111, , 51-60, Se 1, 2, 4, 51-59, 91, , 111, , 51-59, Se 1, 2, 4, 16, 17, 22, 28, 32, 51-79, 91, , 251 2, 16, 17, 22, 28, 32, 51-79, 91 16, 17, 22, 28, 32, Se 1, 2, 4, 51-58, 91, , 111, , 51-58, Se 1, 2, 4, 51-53, 91, , 111, , 51-53, Br 1, 2, 4, 51-61, 91, , 111, , 51-61, Br 1, 2, 4, 51-54, 91, , 111, , 51-54, Kr 1, 2, 4, 16, 51-53, 91, , 111, , 16, 51-53, 91 16, Kr 1, 2, 4, 16, 51-56, 91, , 111, , 16, 51-56, 91 16, Kr 1, 2, 4, 16, 51-59, 91, , 111, , 16, 51-59, 91 16, 91 30

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 83 Kr 1, 2, 4, 16, 17, 51-56, 91, , 111, , 16, 17, 51-56, 91 16, 17, Kr 1, 2, 4, 16, 51-63, 91, , 111, , 16, 51-63, 91 16, Kr 1, 2, 4, 51, 91, , 111 2, 51, Kr 1, 2, 4, 16, 17, 51-64, 91, , 111, , 16, 17, 51-64, 91 16, 17, Rb 1, 2, 4, 51-53, 91, , 111, , 51-53, Rb 1, 2, 4, 51, 91, , 111 2, 51, Rb 1, 2, 4, 51, 52, 91, , 111, , 51, 52, Sr 1, 2, 4, 91, , 111 2, Sr 1, 2, 4, 51-57, 91, , 111, , 51-57, Sr 1, 2, 4, 51-57, 91, , 111, , 51-57, Sr 1, 2, 4, 51-55, 91, , 111, , 51-55, Sr 1, 2, 4, 51-62, 91, , 111 2, 51-62, Sr 1, 2, 4, 51-54, 91, , 111 2, 51-54, Y 1, 2, 4, 16, 22, 28, 51-62, 91, , 16, 22, 28, 51-62, 91 16, 22, 28, Y 1, 2, 4, 51, 52, 91, , 111 2, 51, 52, Y 1, 2, 4, 51-58, 91, 102, , 111 2, 51-58, Zr 1, 2, 4, 16, 22, 28, 32, 51-57, 91, , 111, 251 2, 16, 22, 28, 32, 51-57, 91 16, 22, 28, 32, Zr 1, 2, 4, 16, 17, 22, 28, 32, 51-64, 91, , 251 2, 16, 17, 22, 28, 32, 51-64, 91 16, 17, 22, 28, 32, Zr 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-67, 91, , 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, , , Zr 1, 2, 4, 16, 22, 28, 51-62, 91, , 111, 251, 252 2, 16, 22, 28, 51-62, 91 16, 22, 28, Zr 1, 2, 4, 16, 17, 22, 28, 32, 51-64, 91, , 107, 2, 16, 17, 22, 28, 32, 51-64, 91 16, 17, 22, 28, 32, Reactions with energy-angle distributions in MF=6 95 Zr 1, 2, 4, 16, 51-64, 91, , 111, 251, 252 2, 16, 51-64, 91 16, Zr 1, 2, 4, 16, 17, 22, 28, 51-57, 91, , 107, 251 2, 16, 17, 22, 28, 51-57, 91 16, 17, 22, 28, Nb 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-73, 91, , 107 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, , Mo 1, 2, 4, 16, 22, 28, 51-66, 91, , 111, , 2, , 22, 28, 91,

32 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 94 Mo 1, 2, 4, 16, 17, 22, 28, 51-69, 91, , 111, 2, , 17, 22, 28, 91, , Mo 1, 2, 4, 16, 17, 22, 28, 51-65, 91, , , 2, , 17, 22, 28, 91, Mo 1, 2, 4, 16, 17, 22, 28, 51-67, 91, , 107, 2, , 17, 22, 28, 91, , , 207, Mo 1, 2, 4, 16, 17, 22, 28, 51-63, 91, , , 2, , 17, 22, 28, 91, Mo 1, 2, 4, 16, 17, 22, 28, 51-64, 91, , 107, 2, , 17, 22, 28, 91, , , 207, Mo 1, 2, 4, 51-56, 91, , 111 2, 51-56, Mo 1, 2, 4, 16, 17, 22, 28, 51-54, 91, , 107, , 207, Tc 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-60, 91, , 251 2, 16, 17, 22, 28, 32, 33, 51-60, 91 2, , 17, 22, 28, 91, , , 17, 22, 28, 32, 33, Ru 1, 2, 4, 91, , 111, , Ru 1, 2, 4, 91, , 111, , Ru 1, 2, 4, 51-62, 91, , 111, , 51-62, Ru 1, 2, 4, 51-57, 91, , 111, , 51-57, Ru 1, 2, 4, 16, 17, 22, 28, 51-65, 91, 102, 103, 107, 2, 16, 17, 22, 28, 51-65, 91 16, 17, 22, 28, Ru 1, 2, 4, 51-69, 91, , 111 2, 51-69, Ru 1, 2, 4, 16, 51-89, 91, , 111, 251, 252 2, 16, 51-89, 91 16, Ru 1, 2, 4, 51, 52, 91, , 111, , 51, 52, Ru 1, 2, 4, 51-59, 91, , 111 2, 51-59, Ru 1, 2, 4, 51-54, 91, , 111 2, 51-54, Rh 1, 2, 4, 16, 51-64, 91, 102 2, 16, 51-64, 91 16, Rh 1, 2, 4, 51-53, 91, 102 2, 51-53, Pd 1, 2, 4, 91, , 111, , Pd 1, 2, 4, 16, 51-64, 91, , 111, 251, 252 2, 16, 51-64, 91 16, 91 32

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=5 105 Pd 1, 2, 4, 16, 51-91, , 111, 251, 252 2, 16, , Pd 1, 2, 4, 16, 51-70, 91, , 111, 251, 252 2, 16, 51-70, 91 16, Pd 1, 2, 4, 16, 51-67, 91, , 111, 251, 252 2, 16, 51-67, 91 16, Pd 1, 2, 4, 16, 51-60, 91, , 111, 251, 252 2, 16, 51-60, 91 16, Pd 1, 2, 4, 16, 51-60, 91, , 111, 251, 252 2, 16, 51-60, 91 16, Ag 1, 2, 4, 16, 51-56, 91, , 111, , 16, 51-56, 91 16, Ag 1, 2, 4, 16, 51-64, 91, , 111, 251, 252 2, 16, 51-64, 91 16, Ag 1, 2, 4, 51-60, 91, , 111 2, 51-60, Cd 1, 2, 4, 16, 22, 28, 32, 33, 51-55, 91, , 16, 22, 28, 32, 33, 51-55, 91 16, 22, 28, 32, 33, Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-60, 91, , 16, 17, 22, 28, 32, 33, 51-60, Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-64, 91, , 16, 17, 22, 28, 32, 33, 51-64, Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-61, 91, , 16, 17, 22, 28, 32, 33, 51-61, Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-58, 91, , 16, 17, 22, 28, 32, 33, 51-58, Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-62, 91, , 16, 17, 22, 28, 32, 33, 51-62, Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-60, 91, , 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, m Cd 1, 2, 4, 91, , 111 2, Cd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-56, 91, , 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, , In 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-74, 91, , 251 2, 16, 17, 22, 28, 32, 33, 51-74, In 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-63, 91, , 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, Sn 1, 2, 4, 16, 17, 22, 28, 51-73, 91, , 111 2, 16, 17, 22, 28, 51-73, 91 16, 17, 22, 28, Sn 1, 2, 4, 16, 17, 22, 28, 51-76, 91, , 16, 17, 22, 28, 51-76, 91 16, 17, 22, 28, 91 Reactions with energy-angle distributions in MF=6 33

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 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, , 16, 17, 22, 28, 32, 51-66, 91 16, 17, 22, 28, 32, Sn 1, 2, 4, 16, 17, 22, 28, 51-60, 91, , 107 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, Sn 1, 2, 4, 16, 17, 22, 28, 32, 51-62, 91, , 107 2, 16, 17, 22, 28, 32, 51-62, 91 16, 17, 22, 28, 32, Sn 1, 2, 4, 16, 17, 22, 28, 51-57, 91, , 107 2, 16, 17, 22, 28, 51-57, 91 16, 17, 22, 28, Sn 1, 2, 4, 16, 17, 22, 28, 32, 51-70, 91, , 107 2, 16, 17, 22, 28, 32, 51-70, 91 16, 17, 22, 28, 32, Sn 1, 2, 4, 16, 17, 22, 28, 51-66, 91, , 107 2, 16, 17, 22, 28, 51-66, 91 16, 17, 22, 28, Sn 1, 2, 4, 16, 17, 22, 28, 51-59, 91, , 107 2, 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, Sn 1, 2, 4, 51-59, 91, , 111 2, 51-59, Sn 1, 2, 4, 16, 17, 22, 28, 51-70, 91, , 107 2, 16, 17, 22, 28, 51-70, 91 16, 17, 22, 28, Sn 1, 2, 4, 51-53, 91, , 111 2, 51-53, Sn 1, 2, 4, 51-60, 91, , 111 2, 51-60, Sb 1, 2, 4, 16, 17, 22, 28, 51-63, 91, , 107, 251 2, 16, 17, 22, 28, 51-63, 91 16, 17, 22, 28, Sb 1, 2, 4, 16, 17, 22, 28, 51-58, 91, , 107, 251 2, 16, 17, 22, 28, 51-58, 91 16, 17, 22, 28, Sb 1, 2, 4, 51-58, 91, , 107, 111 2, 51-58, Sb 1, 2, 4, 51-69, 91, , 111 2, 51-69, Sb 1, 2, 4, 51-55, 91, , 111 2, 51-55, Te 1, 2, 4, 91, , 111, , Te 1, 2, 4, 51-54, 91, , 111, , 51-54, Te 1, 2, 4, 51-58, 91, , 111, , 51-58, Te 1, 2, 4, 51-61, 91, , 111, , 51-61, Te 1, 2, 4, 51-56, 91, , 111, , 51-56, Te 1, 2, 4, 51-63, 91, , 111, , 51-63, m Te 1, 2, 4, 91, 102 2, Te 1, 2, 4, 51-59, 91, , 111, 251 2, 51-59, m Te 1, 2, 4, 91, , 111 2, Te 1, 2, 4, 51-60, 91, , 111, , 51-60, Te 1, 2, 4, 51-56, 91, , 111 2, 51-56, I 1, 2, 4, 16, 51-62, 91, , 111, 251, 252 2, 16, 51-62, 91 16, 91 Reactions with energy-angle distributions in MF=6 34

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=3 129 I 1, 2, 4, 16, 17, 22, 28, 51-60, 91, 102, 103, 107, 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, I 1, 2, 4, 91, , 111 2, I 1, 2, 4, 51-54, 91, , 111 2, 51-54, I 1, 2, 4, 91, 102 2, Xe 1, 2, 4, 16, 17, 51-54, 91, , 111 2, 16, 17, 51-54, 91 16, 17, Xe 1, 2, 4, 16, 17, 51-54, 91, , 111 2, 16, 17, 51-54, 91 16, 17, Xe 1, 2, 4, 16, 17, 51-53, 91, , 111 2, 16, 17, 51-53, 91 16, 17, Xe 1, 2, 4, 16, 17, 51-56, 91, , 111 2, 16, 17, 51-56, 91 16, 17, Xe 1, 2, 4, 16, 17, 51-56, 91, , 111 2, 16, 17, 51-56, 91 16, 17, Xe 1, 2, 4, 16, 17, 51-56, 91, , 111, , 16, 17, 51-56, 91 16, 17, Xe 1, 2, 4, 16, 17, 51-54, 91, , 111, , 16, 17, 51-54, 91 16, 17, Xe 1, 2, 4, 51, 91, , 111 2, 51, Xe 1, 2, 4, 16, 17, 51-53, 91, , 111, , 16, 17, 51-53, 91, 16, 17, Xe 1, 2, 4, 51, 91, 102 2, 51, 91, Xe 1, 2, 4, 16, 17, 51-53, 91, , 111 2, 16, 17, 51-53, 91 16, 17, Cs 1, 2, 4, 16, 51-55, 91, 102, 103, 107 2, 16, 51-55, 91 16, Cs 1, 2, 4, 51-55, 91, , 111, , 51-55, Cs 1, 2, 4, 16, 51-68, 91, , 111, 251, 252 2, 16, 51-68, 91 16, Cs 1, 2, 4, 91, , 111, , Cs 1, 2, 4, 16, 51-60, 91, , 111, 251, 252 2, 16, 51-60, 91 16, Ba 1, 2, 4, 16, 17, 22, 28, 32, 51-57, 91, , 111 2, 16, 17, 22, 28, 32, 51-57, 91 16, 17, 22, 28, 32, Ba 1, 2, 4, 16, 17, 22, 28, 51-60, 91, , 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, Ba 1, 2, 4, 16, 17, 22, 28, 51-63, 91, , 107, 251 2, 16, 17, 22, 28, 51-63, 91 16, 17, 22, 28, Ba 1, 2, 4, 16, 17, 22, 28, 32, 51-57, 91, , 251 2, 16, 17, 22, 28, 32, 51-57, 91 16, 17, 22, 28, 32, Ba 1, 2, 4, 16, 17, 22, 28, 51-60, 91, , 107, 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, Ba 1, 2, 4, 16, 17, 22, 28, 32, 51-58, 91, , 107, 2, 16, 17, 22, 28, 32, 51-58, 91 16, 17, 22, 28, 32, Ba 1, 2, 4, 16, 17, 22, 28, 51-69, 91, , 107, 251 2, 16, 17, 22, 28, 51-69, 91 16, 17, 22, 28, 91 Reactions with energy-angle distributions in MF=6 35

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=5 140 Ba 1, 2, 4, 16, 17, 91, , 111, 251, 252 2, 16, 17, 91 16, 17, La 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-65, 91, , 251 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, , La 1, 2, 4, 16, 51-73, 91, , 111, 251, 252 2, 16, 51-73, 91 16, La 1, 2, 4, 51-56, 91, 102, , 111 2, 51-56, Ce 1, 2, 4, 51-58, 91, , 111 2, 51-58, Ce 1, 2, 4, 16, 51-62, 91, , 111, 251, 252 2, 16, 51-62, 91 16, Ce 1, 2, 4, 16, 17, 51-56, 91, , 111, 251, 252 2, 16, 17, 51-56, 91 16, 17, Ce 1, 2, 4, 91, , 111 2, Ce 1, 2, 4, 16, 17, 51-68, 91, , 111, 251, 252 2, 16, 17, 51-68, 91 16, 17, Pr 1, 2, 4, 16, 51-74, 91, , 111, 251, 252 2, 16, 51-74, 91 16, Pr 1, 2, 4, 91, , 111 2, Pr 1, 2, 4, 51-56, 91, , 111 2, 51-56, Nd 1, 2, 4, 51-58, 91, , 111, , 51-58, Nd 1, 2, 4, 16, 51-76, 91, , 111, 251, 252 2, 16, 51-76, 91 16, Nd 1, 2, 4, 16, 51-64, 91, , 111, 251, 252 2, 16, 51-64, 91 16, Nd 1, 2, 4, 16, 51-64, 91, , 111, 251, 252 2, 16, 51-64, 91 16, Nd 1, 2, 4, 16, 51-63, 91, , 111, 251, 252 2, 16, 51-63, 91 16, Nd 1, 2, 4, 51-53, 91, , 111, , 51-53, Nd 1, 2, 4, 16, 51-57, 91, , 111, 251, 252 2, 16, 51-57, 91 16, Nd 1, 2, 4, 16, 17, 22, 28, 51-59, 91, , 111, , 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, Pm 1, 2, 4, 16, 51-61, 91, , 111, 251, 252 2, 16, 51-61, 91 16, Pm 1, 2, 4, 91, 102 2, m Pm 1, 2, 4, 91, 102, , Pm 1, 2, 4, 51-56, 91, , 111 2, 51-56, Pm 1, 2, 4, 51-56, 91, , 111 2, 51-56, Sm 1, 2, 4, 91, , 111, , Sm 1, 2, 4, 16, 51-64, 91, , 111, 251, 252 2, 16, 51-64, 91 16, 91 Reactions with energy-angle distributions in MF=6 36

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=5 148 Sm 1, 2, 4, 51-66, 91, , 111 2, 51-66, Sm 1, 2, 4, 16, 17, 51-60, 91, 102, 103, 107 2, 16, 17, 51-60, 91 16, 17, Sm 1, 2, 4, 51-66, 91, , 111, , 51-66, Sm 1, 2, 4, 16, 51-91, , 111, 251, 252 2, 16, , Sm 1, 2, 4, 16, 51-63, 91, , 111, 251, 252 2, 16, 51-63, 91 16, Sm 1, 2, 4, 51-62, 91, , 111 2, 51-62, Sm 1, 2, 4, 51-69, 91, , 111, , 51-69, Eu 1, 2, 4, 16, 17, 22, 28, 51-59, 91, , 111 2, 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, Eu 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-61, 91, , 251 2, 16, 17, 22, 28, 32, 33, 16, 17, 22, 28, 32, 33, , 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, Eu 1, 2, 4, 16, 17, 22, 28, 51-55, 91, , 16, 17, 22, 28, 51-55, 91 16, 17, 22, 28, Eu 1, 2, 4, 16, 17, 22, 28, 51-59, 91, , 16, 17, 22, 28, 51-59, 91 16, 17, 22, 28, Eu 1, 2, 4, 51-55, 91, , 111 2, 51-55, Eu 1, 2, 4, 91, 102 2, Gd 1, 2, 4, 16, 17, 22, 28, 32, 33, 51-79, 91, , 251 2, 16, 17, 22, 28, 32, 33, 51-79, Gd 1, 2, 4, 51-65, 91, , 111 2, 51-65, Gd 1, 2, 4, 51-79, 91, , 111, 251 2, 51-79, Gd 1, 2, 4, 16, 51-64, 91, , 111 2, 16, 51-64, 91 16, Gd 1, 2, 4, 51-78, 91, , 111, 251 2, 51-78, Gd 1, 2, 4, 51-61, 91, , 111 2, 51-61, Gd 1, 2, 4, 51-56, 91, , 107 2, 51-56, Tb 1, 2, 4, 16, 51-66, 91, 102, 251, 252 2, 16, 51-66, 91 16, Tb 1, 2, 4, 91, 102, , Dy 1, 2, 4, 51-64, 91, 102, , 51-64, Dy 1, 2, 4, 51-57, 91, 102, , 51-57, Dy 1, 2, 4, 51-56, 91, 102, , 51-56, Dy 1, 2, 4, 51-56, 91, 102, , 51-56, , 17, 22, 28, 32, 33, 91 Reactions with energy-angle distributions in MF=6 37

38 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, , 16, 17, 51-62, 91 16, 17, Ho 1, 2, 4, 16, 17, 37, 51-63, 91, 102 2, 16, 17, 37, 51-63, 91 16, 17, 37, Er 1, 2, 4, 16, 17, 28, 51-58, 91, 102, 103, 107, , 16, 17, 28, 51-58, 91 16, 17, 28, Er 1, 2, 4, 16, 17, 28, 51-60, 91, 102, 103, 107, , 16, 17, 28, 51-60, 91 16, 17, 28, Er 1, 2, 4, 16, 17, 51-57, 91, 102, 103, 107, , 16, 17, 51-57, 91 16, 17, Er 1, 2, 4, 16, 17, 28, 51-57, 91, 102, 103, 107, , 16, 17, 28, 51-57, 91 16, 17, 28, Er 1, 2, 4, 16, 17, 28, 51-59, 91, 102, 103, 107, , 16, 17, 28, 51-59, 91 16, 17, 28, Er 1, 2, 4, 16, 17, 28, 51-57, 91, 102, 103, 107, , 16, 17, 28, 51-57, 91 16, 17, 28, Lu 1, 2, 4, 16, 17, 51-58, 91, 102, 103, 107, , 16, 17, 51-58, 91 16, 17, Lu 1, 2, 4, 16, 17, 51-58, 91, 102, 103, 107, , 16, 17, 51-58, 91 16, 17, Hf 1, 2, 4, 16, 17, 51-68, 91, 102, 251 2, 16, 17, 51-68, 91 16, 17, Hf 1, 2, 4, 16, 17, 51-73, 91, 102, 103, 107, 251 2, 16, 17, 51-73, 91 16, 17, Hf 1, 2, 4, 16, 17, 51-66, 91, 102, 103, 107, 251 2, 16, 17, 51-66, 91 16, 17, Hf 1, 2, 4, 16, 17, 51-71, 91, 102, 103, 107, 251 2, 16, 17, 51-71, 91 16, 17, Hf 1, 2, 4, 16, 17, 51-62, 91, 102, 103, 107, 251 2, 16, 17, 51-62, 91 16, 17, Hf 1, 2, 4, 16, 17, 51-61, 91, 102, 103, 107, 251 2, 16, 17, 51-61, 91 16, 17, Ta 1, 2, 4, 16, 17, 28, 51-64, 91, 102, 103, 107, 251 2, 16, 17, 28, 51-64, 91 16, 17, 28, Ta1 1, 2, 4, 16, 17, 51-58, 91, 102, 107, , 16, 17, 51-58, 91 16, 17, W 1, 2, 4, 16, 17, 22, 28, 51-70, 91, , 107, 251 2, 16, 17, 22, 28, 51-70, 91 16, 17, 22, 28, W 1, 2, 4, 16, 17, 22, 28, 51-60, 91, , 107, 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, W 1, 2, 4, 16, 17, 22, 28, 51-60, 91, , 107, 251 2, 16, 17, 22, 28, 51-60, 91 16, 17, 22, 28, W 1, 2, 4, 16, 17, 22, 28, 51-62, 91, , 107, 251 2, 16, 17, 22, 28, 51-62, 91 16, 17, 22, 28, Re 1, 2, 4, 16, 17, 51-59, 91, 102 2, 16, 17, 51-59, 91 16, 17, 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, , 16, 17, 51-67, 91 16, 17, 91 nat Ir 1, 2, 4, 16, 17, 51-58, 91, 102, 103, 107, , 16, 17, 51-58, 91 16, 17, 91 nat Pt 1, 2, 4, 16, 17, 91, 102, , 17, 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, , 107 2, 51-80, 16, 17, 22, 28, 91 38

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