ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

[1]  N. M. Larson.  Treatment of Data Uncertainties , 2005 .

[2]  R.E. MacFarlane,et al.  The NJOY Nu-clear Data Processing System Version 91 , 1994 .

[3]  D. Rochman,et al.  MODELING AND FISSION CROSS SECTIONS FOR AMERICIUM. , 2005 .

[4]  K. Kratz,et al.  New calculations of grossβ-decay properties for astrophysical applications: Speeding-up the classicalrprocess , 2003 .

[5]  K. D. Watts,et al.  Measurement of β−-decay intensity distributions of several fission-product isotopes using a total absorption γ-ray spectrometer , 1997 .

[6]  D. G. Madland,et al.  Recent results in the development of a global medium-energy nucleon-nucleus optical-model potential , 1988 .

[7]  Donald L. Smith,et al.  Probability, statistics, and data uncertainties in nuclear science and technology , 1991 .

[8]  Darryl B. Smith,et al.  He3+t Reactions , 1962 .

[9]  N. M. Larson,et al.  An International Evaluation of the Neutron Cross Section Standards , 2006 .

[10]  Danas Ridikas,et al.  Photonuclear Physics in Radiation Transport—III: Actinide Cross Sections and Spectra , 2006 .

[11]  Ken Nakajima,et al.  Re-evaluation of the Effective Delayed Neutron Fraction Measured by the Substitution Technique for a Light Water Moderated Low-enriched Uranium Core , 2001 .

[12]  Arjan J. Koning,et al.  Local and global nucleon optical models from 1 keV to 200 MeV , 2003 .

[13]  Darryl B. Smith,et al.  He$sup 3$ + t REACTIONS , 1963 .

[14]  W. B. Wilson,et al.  Delayed neutron study using ENDF/B-VI basic nuclear data , 2002 .

[15]  S. Raman,et al.  Dirac–Fock Internal Conversion Coefficients , 2002 .

[16]  R. J. Dupzyk,et al.  239Pu and 241Am (n, 2n) cross-section measurements near En = 14 MeV , 2002 .

[17]  R. W. Peelle,et al.  The ENDFB-VI neutron cross section measurement standards , 1993 .

[18]  A. Hasegawa,et al.  Evaluation of the unresolved resonance range of 238U , 2002 .

[19]  Mark D. DeHart,et al.  Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages , 1996 .

[20]  K. Kratz,et al.  Status of delayed-neutron precursor data: half-lives and neutron emission probabilities , 2001, nucl-ex/0106020.

[21]  W. D. George,et al.  NEUTRON YIELDS FROM TARGETS BOMBARDED BY ELECTRONS , 1959 .

[22]  Benjamin Morillon,et al.  Overview of Recent Bruyères‐le‐Châtel Actinide Evaluations , 2005 .

[23]  M. Descalle,et al.  Neutron and photon transport in seagoing cargo containers , 2004 .

[24]  G. Hale,et al.  Cross sections and spectra for charged-particle induced reactions , 1994 .

[25]  E. Pitcher,et al.  Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes , 2006 .

[26]  M. Stepanov,et al.  Atlas of Giant Dipole Resonances. Parameters and Graphs of Photonuclear Reaction Cross Sections , 1999 .

[27]  T. Houk.  NEUTRON--PROTON SCATTERING CROSS SECTION AT A FEW ELECTRON VOLTS AND CHARGE INDEPENDENCE. , 1971 .

[28]  R. R. Kinsey,et al.  Guidebook for the ENDF/B-V nuclear data files , 1982 .

[29]  Mark B. Chadwick,et al.  Photonuclear Physics in Radiation Transport—II: Implementation , 2003 .

[30]  Isabel S. Gonçalves,et al.  Neutron capture cross section of Th-232 measured at the n_TOF facility at CERN in the unresolved resonance region up to 1-MeV , 2006 .

[31]  Herman Feshbach,et al.  The statistical theory of multi-step compound and direct reactions , 1980 .

[32]  V. Tikku,et al.  Neutron widths and level spacings of 64 Zn+n , 1981 .

[33]  P. Schillebeeckx,et al.  Measurement of the Subthermal Neutron Induced Fission Cross Section of 241Pu , 1992 .

[34]  C. Glashausser,et al.  POLARIZATION PHENOMENA IN NUCLEAR REACTIONS. , 1969 .

[35]  H. C. Wu,et al.  Nuclear Data for Science and Technology , 1998 .

[36]  G. Vineyard.  Frequency factors and isotope effects in solid state rate processes , 1957 .

[37]  Nancy M Larson,et al.  VALIDATION OF MULTIPLE-SCATTERING CORRECTIONS IN THE ANALYSIS CODE SAMMY , 2002 .

[38]  J. D. Anderson,et al.  Neutron spectrum from the T+T reaction , 1965 .

[39]  E. Melkonian,et al.  Measurement of the 2200 m/sec neutron-proton capture cross section , 1977 .

[40]  H. Liskien,et al.  Systematic Studies of Excitation Functions of (n, t) Reactions on Medium and Heavy Mass Nuclei , 1990 .

[41]  A. Koning,et al.  ECISVIEW : An interactive toolbox for optical model development , 1997 .

[42]  E. Plechaty,et al.  AN INTEGRATED SYSTEM FOR PRODUCTION OF NEUTRONICS AND PHOTONICS CALCULATIONAL CONSTANTS. VOLUME VI. PHOTON CROSS SECTIONS 1 keV TO 100 MeV. , 1968 .

[43]  D. Madland,et al.  Prompt fission neutron spectra and average prompt neutron multiplicities , 1982 .

[44]  F. Käppeler,et al.  Stellar neutron capture cross sections of the Cd isotopes , 1995 .

[45]  F. Hambsch,et al.  An Interpretation of Energy Dependence of Delayed Neutron Yields in the Resonance Region for 235U and 239Pu , 2004 .

[46]  P. F. Rose,et al.  ENDF-201: ENDF/B-VI summary documentation , 1991 .

[47]  H. Gerstenberg,et al.  Photonuclear data - abstract sheets 1955 - 1982 volume VI (aluminum - phosphorous) , 1984 .

[48]  Jonghwa Chang,et al.  Neutron Cross-Section Evaluations of Fission Products in the Fast Energy Region , 2002 .

[49]  Kokoo,et al.  Measurements of double-differential cross sections of charged-particle emission reactions for several structural elements of fusion power reactors by 14.1-MeV incident neutrons , 1999 .

[50]  W. Younes,et al.  Neutron-induced fission cross sections simulated from (t,pf) results , 2003 .

[51]  D. Brown,et al.  Proposal for ENDF formats that describe emission of post-fission beta-delayed photons , 2004 .

[52]  M. W. Herman,et al.  Recent Developments of the Nuclear Reaction Model Code EMPIRE , 2005 .

[53]  L. C. Leal,et al.  R-MATRIX RESONANCE ANALYSIS AND STATISTICAL PROPERTIES OF THE RESONANCE PARAMETERS OF 233U IN THE NEUTRON ENERGY RANGE FROM THERMAL TO 600 eV , 2001 .

[54]  H. D. Ferguson,et al.  NUCLEAR LEVEL DENSITIES IN INTERMEDIATE AND HEAVY NUCLEI. , 1967 .

[55]  H. Argo,et al.  t-t ELASTIC SCATTERING FROM 1.6 TO 2.0 MEV , 1956 .

[56]  Young,et al.  Multiple preequilibrium emission in Feshbach-Kerman-Koonin analyses. , 1994, Physical review. C, Nuclear physics.

[57]  N. M. Larson,et al.  An Unresolved Resonance Evaluation for 235 U , 2004 .

[58]  J. H. Hubbell,et al.  Tables and graphs of atomic subshell and relaxation data derived from the LLNL Evaluated Atomic Data Library (EADL), Z=1-100 , 1991 .

[59]  F. Ajzenberg‐Selove.  Energy levels of light nuclei A = 13-15 , 1991 .

[60]  N. M. Larson,et al.  An Unresolved Resonance Evaluation for 233 U from 600 eV to 40 keV , 2005 .

[61]  C. L. Dunford,et al.  Evaluated Nuclear Data File, ENDF/B-VI , 1992 .

[62]  Shigeaki Okajima,et al.  Summary on international benchmark experiments for effective delayed neutron fraction (βeff) , 2002 .

[63]  Tadashi Yoshida,et al.  Reconsideration of the Theoretical Supplementation of Decay Data in Fission Product Decay Heat Summation Calculations , 2006 .

[64]  Uhl,et al.  Test of gamma-ray strength functions in nuclear reaction model calculations. , 1990, Physical review. C, Nuclear physics.

[65]  C. Porter,et al.  Fluctuations of Nuclear Reaction Widths , 1956 .

[66]  L. Streit,et al.  Models and Methods in Few-Body Physics , 1987 .

[67]  L. Almqvist,et al.  Phonon-Frequency Distributions and Heat Capacities of Aluminum and Lead , 1967 .

[68]  C. Papadopoulos,et al.  Measurement of the Am241(n,2n) reaction cross section using the activation method , 2006 .

[69]  R. Capote,et al.  Is a global coupled-channel dispersive optical model potential for actinides feasible? , 2005 .

[70]  D. Madland.  International Evaluation Co-operation - Volume 9: Fission Neutron Spectra of Uranium-235 , 2003 .

[71]  R. E. Schenter,et al.  Beta decay properties using a statistical model , 1982 .

[72]  J. Young,et al.  Slow neutron scattering by molecular hydrogen and deuterium. , 1964 .

[73]  L. Leal,et al.  Reevaluation and Validation of the 241Pu Resonance Parameters in the Energy Range Thermal to 20 eV , 2005 .

[74]  Mark B. Chadwick,et al.  Comprehensive nuclear model calculations: Introduction to the theory and use of the GNASH code , 1992 .

[75]  C. M. Logan,et al.  LIVERMORE PULSED SPHERE PROGRAM: PROGRAM SUMMARY THROUGH JULY 1971. , 1972 .

[76]  M. C. Brady.  Evaluation and application of delayed neutron precursor data , 1989 .

[77]  E. Arthur,et al.  GNASH: a preequilibrium, statistical nuclear-model code for calculation of cross sections and emission spectra. [In FORTRAN for CDC 7600] , 1977 .

[78]  R. Capote,et al.  Improvement of the Fission Channel in the EMPIRE Code , 2005 .

[79]  B. C. Diven,et al.  Neutron Capture to Fission Ratios in U233, U235, Pu233 , 1962 .

[80]  R. Capote,et al.  Dispersive coupled-channel analysis of nucleon scattering from 232 Th up to 200 MeV , 2005 .

[81]  W. Dilg.  Measurement of the neutron-proton total cross section at 132 eV , 1975 .

[82]  R. E. MacFarlane,et al.  New thermal neutron scattering files for ENDF/B-VI release 2 , 1994 .

[83]  Pavel Oblozinsky,et al.  SG21: Assessment of Neutron Cross-Section Evaluations for the Bulk of Fission Products , 2004 .

[84]  G. Mertens,et al.  Measurement of the Neutron-Proton Differential Cross Section at 14.1 MeV , 1997 .

[85]  Z. Jing-Shang,et al.  Formation and Emission of Light particles in Fast Neutron Induced Reaction—A Unified Compound Pre-Equilibrium Model(2) , 1988 .

[86]  A. Santamarina,et al.  Trends in Nuclear Data Derived from Integral Experiments in Thermal and Epithermal Reactors , 2002 .

[87]  Arnaud Courcelle,et al.  First Conclusions of the WPEC/Subgroup‐22 Nuclear Data for Improved LEU‐LWR Reactivity Predictions , 2005 .

[88]  A. Ventura,et al.  Fission of Light Actinides: 232Th(n,f) and 231Pa(n,f) Reactions , 2006 .

[89]  H. Weaver,et al.  Measurement of the Uranium-238 Capture Cross Section for Incident Neutron Energies up to 100 keV , 1973 .

[90]  T. R. England,et al.  Evaluation and compilation of fission product yields 1993 , 1995 .

[91]  H. Weidenmüller,et al.  Multistep-compound contribution to precompound reaction cross section , 1992 .

[92]  A. Nichols.  Validation of Fission Product Decay Data for Decay Heat Calculations , 2006 .

[93]  N. M. Larson.  Updated users' guide for SAMMY: multilevel R-matrix fits to neutron data using Bayes' equations. Revision 1 , 1985 .

[94]  V. Maslov.  Uranium symmetric/asymmetric neutron-induced fission up to 200 MeV , 2004 .

[95]  E. Hallman,et al.  Lattice vibrations in iron at 296°K , 1967 .

[96]  T. Udagawa,et al.  Multistep direct reaction analysis of continuum spectra in reactions induced by light ions , 1982 .

[97]  T. Kawano,et al.  Production of isomers by neutron-induced inelastic scattering on 193Ir and influence of spin distribution in the pre-equilibrium process , 2006 .

[98]  A. Santamarina,et al.  Evaluation of 238U Resonance Parameters from 0 to 20 keV , 2005 .

[99]  Blann.  New precompound decay model. , 1996, Physical review. C, Nuclear physics.

[100]  S. E. Aumeier,et al.  The simultaneous evaluation of the standards and other cross sections of importance for technology , 1997 .

[101]  D. Rochman,et al.  New Evaluation of the 99Tc Neutron-Induced Cross Sections for the ENDF/B-VII.0 Library , 2008 .

[102]  J. T. Ward,et al.  The Physical Models and Statistical Procedures Used in the RACER Monte Carlo Code , 1999 .

[103]  D. W. Muir.  Gamma rays, Q-values, and kerma factors , 1976 .

[104]  W. Myers,et al.  Nuclear ground state masses and deformations , 1995 .

[105]  Arjan J. Koning,et al.  TALYS: Comprehensive Nuclear Reaction Modeling , 2005 .

[106]  Stephen M. Seltzer,et al.  Tables and Graphs of Electron-Interaction Cross Sections from 10 eV to 100 GeV Derived from the LLNL Evaluated Data Library (EEDL), Z=1-100 | NIST , 1991 .

[107]  W. Haeberli,et al.  Elastic scattering of 9–13 MeV vector polarized deuterons , 1974 .

[108]  Ohsawa Takaaki,et al.  Possible fluctuations in the delayed neutron yields in the resonance region of U-235 , 2002 .

[109]  H. Derrien.  NEUTRON TOTAL CROSS SECTIONS OF 235U FROM TRANSMISSION MEASUREMENTS IN THE ENERGY RANGE 2 keV to 300 keV AND STATISTICAL MODEL ANALYSIS OF THE DATA , 2000 .

[110]  S. Barshay,et al.  GEOMETRIC TEST OF THE ISOSPIN MULTIPLET NATURE OF NUCLEAR ANALOG STATES , 1964 .

[111]  J. E. Lynn,et al.  The double-humped fission barrier , 1980 .

[112]  A. V. Ignatyuk,et al.  Phenomenological description of energy dependence of the level density parameter , 1975 .

[113]  A. Iwamoto,et al.  Mechanism of cluster emission in nucleon-induced preequilibrium reactions , 1982 .

[114]  C. Beausang,et al.  Estimation of ( n, f ) Cross Sections by Measuring Reaction Probability Ratios , 2005 .

[115]  S. A. Werner,et al.  Precision neutron interferometric measurements and updated evaluations of the n-p and n-d coherent neutron scattering lengths , 2003 .

[116]  S. Ohki,et al.  Target accuracy of MA nuclear data and progress in validation by post irradiation experiments with the fast reactor “JOYO” , 2003 .

[117]  F. M. Mann,et al.  Phenomenology of continuum angular distributions. I. Systematics and parametrization , 1981 .

[118]  A. A. Llnl Marchetti,et al.  New Monte Carlo simulations of the LLNL pulsed-sphere experiments , 1998 .

[119]  M. C. Brady,et al.  Delayed Neutron Data and Group Parameters for 43 Fissioning Systems , 1989 .

[120]  Kazuteru Sugino,et al.  Development of a Unified Cross-section Set ADJ2000 based on Adjustment Technique for Fast Reactor Analysis , 2002 .

[121]  S. T. Perkins,et al.  Tables and graphs of electron-interaction cross sections from 10 eV to 100 GeV derived from the LLNL Evaluated Electron Data Library (EEDL), Z = 1--100 , 1991 .

[122]  Fred B. Bateman,et al.  Measurement of the n - p elastic scattering angular distribution at E n = 10 MeV , 2002 .

[123]  J. W. Tepel,et al.  Hauser-Feshbach calculations in the presence of weakly absorbing channels with special reference to the elastic enhancement factor and the factorization assumption , 1980 .

[124]  A. H. Wapstra,et al.  The Nubase evaluation of nuclear and decay properties , 2003 .

[125]  D. Olsen,et al.  Measurement of neutron-transmission spectra through /sup 232/Th from 8 MeV to 4 keV , 1981 .

[126]  Allan D. Carlson,et al.  Status of the Neutron Cross-Section Standards Database , 2005 .

[127]  Axel,et al.  ELECTRIC DIPOLE GROUND STATE TRANSITION WIDTH STRENGTH FUNCTION AND 7 MEV PHOTON INTERACTIONS. Technical Report No. 30 , 1962 .

[128]  Peter Meyer,et al.  Giant resonance for the actinide nuclei: Photoneutron and photofission cross sections for U-235, U-236, U-238, and Th-232 , 1980 .

[129]  Boris Pritychenko,et al.  Nuclear reaction and structure data services of the National Nuclear Data Center , 2006 .

[130]  C. Kalbach.  The Griffin model, complex particles and direct nuclear reactions , 1977 .

[131]  G. R. Satchler,et al.  Optical-model analysis of the scattering of 24.7 MeV alpha particles , 1966 .

[132]  Willis,et al.  Precision measurement of the bound-coherent-neutron scattering length of 235U. , 1987, Physical review. A, General physics.

[133]  M. Sowerby.  Summary of the work of the neandc task force on U-238 , 1986 .

[134]  J. H. Todd,et al.  Subthreshold Fission Cross Section of 240 Pu and the Fission Cross Sections of 235 U and 239 Pu , 1984 .

[135]  Gunter H. R. Kegel,et al.  Prompt fission neutron energy spectra induced by fast neutrons , 1995 .

[136]  J. Becker,et al.  Estimated (n,f) cross sections for 236,236m237,238-Np, 237,237m-Pu, and 240,241,242,242m,243,244,244m-Am isotopes , 2004 .

[137]  B. Moskowitz,et al.  RCPO1 - A Monte Carlo program for solving neutron and photon transport problems in three dimensional geometry with detailed energy description and depletion capability , 2000 .

[138]  R. Roy,et al.  Neutron to proton ratios of quasiprojectile and midrapidity emission in the $^{64}$Zn + $^{64}$Zn reaction at 45 MeV/nucleon , 2006, nucl-ex/0606031.

[139]  Mcneill,et al.  Absolute photoneutron cross sections for Zr, I, Pr, Au, and Pb. , 1987, Physical review. C, Nuclear physics.

[140]  F. H. Fröhner.  Evaluation of the unresolved resonance range of sup 238 U , 1989 .

[141]  S. A. Badikov,et al.  Nuclear Data Processing, Analysis, Transformation and Storage with Pade-Approximants , 1992 .

[142]  B. L. Berman,et al.  Atlas of photoneutron cross sections obtained with monoenergetic photons. Second edition , 1974 .

[143]  Jacobus J. M. Verbaarschot,et al.  Statistical theory of precompound reactions: The multistep compound process , 1986 .

[144]  Makoto Ishikawa,et al.  Recent Application of Nuclear Data to Fast Reactor Core Analysis and Design in Japan , 2005 .

[145]  S. V. D. Marck.  Benchmarking ENDF/B-VII.0 , 2006 .

[146]  D. Rochman,et al.  Modeling and Neutron-Induced Fission Cross Sections for Americium , 2006 .

[147]  N. M. Larson.  On the Efficient Treatment of Data Covariance Matrices , 2004 .

[148]  T. Kawano,et al.  Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes , 2007 .

[149]  G. D. Saussure,et al.  High energy resolution measurement of the /sup 238/U neutron capture yield in the energy region between 1 and 100 keV , 1988 .

[150]  Naohiro Hirakawa,et al.  Measurement of Double-Differential Neutron Emission Spectra from Uranium-238 , 1990 .

[151]  D. Rochman,et al.  New evaluation of V51 (n, np + pn) and V51 (n, t) cross sections for the ENDF/B-VII library , 2006 .

[152]  Total prompt energy release in the neutron-induced fission of 235 U, 238 U, and 239 Pu , 2006, nucl-th/0603071.

[153]  M. Chadwick,et al.  New precompound decay model: Angular distributions , 1998 .

[154]  J. F. Briesmeister.  MCNP-A General Monte Carlo N-Particle Transport Code , 1993 .

[155]  Andrej Trkov,et al.  Revisiting the 238U Thermal Capture Cross Section and Gamma-Ray Emission Probabilities from 239Np Decay , 2005 .

[156]  M. Mattes,et al.  Thermal neutron scattering data for the moderator materials H 2 O, D 2 O and ZrH x in ENDF-6 format and as ACE library for MCNP(X) codes , 2005 .

[157]  P. Moldauer.  Evaluation of the fluctuation enhancement factor , 1976 .

[158]  E. G. Silver,et al.  Precise measurement and analysis of neutron transmission through ²³⁸U , 1977 .

[159]  N. M. Larson,et al.  R-matrix analysis of the 240Pu neutron cross sections in the thermal to 5700-eV energy range , 1990 .

[160]  Mark B. Chadwick,et al.  Photonuclear Physics in Radiation Transport—I: Cross Sections and Spectra , 2003 .

[161]  ENDF/B-V1 Coupled Photon-Electron Data for Use in Radiation Shielding Applications , 2002 .

[162]  Microscopic calculation of the 4He system , 1996, nucl-th/9608046.

[163]  K. Kratz,et al.  Systematics of neutron emission probabilities from delayed neutron precursors , 1973 .

[164]  R. W. Hockenbury,et al.  MEASUREMENT OF THE NEUTRON FISSION AND CAPTURE CROSS SECTIONS FOR $sup 233$U IN THE ENERGY REGION 0.4 TO 1000 eV. , 1968 .

[165]  R. Q. Wright,et al.  Review of ENDF/B-VI Fission-Product Cross Sections[Evaluated Nuclear Data File] , 2000 .

[166]  R. Haight,et al.  Charged-particle—producing reactions of 15-MeV neutrons on V 51 and Nb 93 , 1978 .

[167]  J. W. Tepel,et al.  ENSDF - The evaluated nuclear structure data file , 1984 .

[168]  J. Keinert,et al.  Investigation of neutron scattering dynamics in liquid hydrogen and deuterium for cold neutron sources / Untersuchung der Neutronenstreudynamik in flüssigem Wasserstoff und Deuterium für Quellen kalter Neutronen , 1987 .

[169]  Kalbach.  Systematics of continuum angular distributions: Extensions to higher energies. , 1988, Physical review. C, Nuclear physics.

[170]  N. M. Larson,et al.  Updated Users' Guide for SAMMY Multilevel R-matrix Fits to Neutron Data Using Bayes' Equation , 1998 .

[171]  P. Obložinský,et al.  Handbook for calculations of nuclear reaction data, RIPL-2 (Reference Input Parameter Library-2) , 2006 .

[172]  J. H. Hubbell,et al.  EPDL97: the evaluated photo data library `97 version , 1997 .

[173]  G. E. Thomas,et al.  p-Wave Resonances of U 238 , 1968 .

[174]  C. Kalbach.  PRECO-D2: program for calculating preequilibrium and direct reaction double differential cross sections , 1985 .

[175]  Z. Chen.  REDUCED R-MATRIX ANALYSIS OF￣(17)O SYSTEM , 1995 .

[176]  Y. Danon,et al.  Neutron Capture and Transmission Measurements and Resonance Parameter Analysis of Niobium , 2002 .

[177]  N. Jarmie,et al.  Fusion-energy reaction H-2 (t, alpha) n from Et=12.5to117 keV , 1984 .

[178]  C. L. Dunford,et al.  A dipole–quadrupole interaction term in E1 photon transitions , 2000 .

[179]  M. Drosg.  Improved evaluation of the differential cross sections of the3H(d,n)4He reaction for deuteron energies between 3 and 7 MeV , 1981 .

[180]  K. Kratz,et al.  Nuclear properties for astrophysical and radioactive-ion-beam applications (II) , 1997, Atomic Data and Nuclear Data Tables.

[181]  E. Gadioli,et al.  Pre-Equilibrium Nuclear Reactions , 1992 .

[182]  J. A. Bucholz,et al.  Improving the LLNL pulsed sphere experiments database and MCNP models. , 2003 .

[183]  H. G. Hughes,et al.  Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX , 1999 .

[184]  M. Devlin,et al.  Prompt-fission-neutron average energy for 238U(n, f) from threshold to 200 MeV , 2003 .

[185]  T. A. Lewis,et al.  High-Resolution Transmission Measurements of 233U Using a Cooled Sample at the Temperature T = 11 K , 2001 .

[186]  G. M. Hale.  Use of R-matrix methods for light element evaluations , 1980 .

[187]  J. Rowlands,et al.  Conclusions concerning the delayed neutron data for the major actinides , 2002 .

[188]  Tokio Fukahori,et al.  Handbook on Photonuclear Data for Applications. Cross Sections and Spectra. IAEA-TECDOC-1178 , 2000 .

[189]  A. Iwamoto,et al.  Pre-equilibrium emission of light composite particles in the framework of the exciton model , 1983 .

[190]  G. D. Saussure,et al.  Ratio of Capture to Fission in U235 at keV Neutron Energies , 1964 .

[191]  P. Gouffon,et al.  Comment on photoneutron cross sections , 1984 .

[192]  Hale,et al.  Neutron-triton cross sections and scattering lengths obtained from p-3He scattering. , 1990, Physical review. C, Nuclear physics.

[193]  Satoshi Chiba,et al.  A suggested procedure for resolving an anomaly in least-squares data analysis known as Peelle's Pertinent Puzzle'' and the general implications for nuclear data evaluation , 1991 .

[194]  D. L. Smith,et al.  Covariance matrices for nuclear cross sections derived from nuclear model calculations. , 2005 .

[195]  R. B. Perez,et al.  Measurement and Resonance Analysis of Neutron Transmission Through Uranium-238 , 1979 .

[196]  C. H. Poppe,et al.  Neutrons from D + T and D + H , 1963 .

[197]  J. W. Tepel,et al.  Direct reactions and Hauser--Feshbach theory , 1975 .

[198]  J Pruet,et al.  Monte Carlo models for the production of β-delayed gamma-rays following fission of special nuclear materials , 2004 .

[199]  D. H. Houston,et al.  REFERENCE MANUAL FOR ENDF THERMAL NEUTRON SCATTERING DATA. , 1968 .

[200]  M. W. Herman,et al.  Fission of light actinides:Th232(n,f) andPa231(n,f) reactions , 2006 .

[201]  R. K. Meulekamp,et al.  Calculating the Effective Delayed Neutron Fraction with Monte Carlo , 2006 .

[202]  M. Chadwick,et al.  Precompound Monte-Carlo model for cluster induced reactions , 2000 .

[203]  O. Iwamoto,et al.  Neutron Cross‐Section Evaluations for 70,72,73,74,76Ge , 2005 .

[204]  A. Koning,et al.  Benchmark Results for Delayed Neutron Data , 2005 .