| ENDF-101 |
X |
T.E.Stephenson, A.Prince, S.Pearlstein |
Evaluation of the Neutron Cross Section of Manganese for the
ENDF/B Library |
Jun 1967 |
BNL-50060 |
| ENDF-102 1966 |
|
H.C.Honeck |
Specifications for an Evaluated Nuclear Data File for REACTOR APPLICATIONS
... |
May 1966 |
BNL-50066 1st Ed. |
| ENDF-102 1970 Vol.1 |
|
M.K.Drake |
Data Formats and Procedures for the ENDF Neutron Cross Section Library
|
Oct 1970 |
BNL-50274 1st Ed. Vol.1 |
| ENDF-102 1970 Vol.2 |
|
D.J.Dudziak |
ENDF Formats and Procedures for Photon Production and Interaction Data
|
Jul 1971 |
LA-4549 1st Ed. Vol.2 |
| ENDF-102 1975 |
|
D.I.Garber |
Data Formats and Procedures for Evaluated Nuclear Data File |
Oct 1975 |
BNL-NCS-50496 2 Ed. |
| ENDF-102 1979 |
|
R.R.Kinsey |
Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF/B-V
|
Oct 1979 |
BNL-NCS-50496 3 Ed. |
| ENDF-102 1980 |
|
S.Pearlstein |
Supp. to the ENDF/B-V Formats and Procedures Manual for Using ENDF/B-IV
... |
Nov 1980 |
BNL-NCS-28949 2 Ed. Suppl. |
| ENDF-102 1983 |
|
B.A.Magurno |
Data Formats and Procedures for the Evaluated Nuclear Data File,
ENDF.V-V |
Nov 1983 |
BNL-NCS-50496 3 Ed. Rev. |
| ENDF-102 1990 |
X |
P.F.Rose, C.L.Dunford |
Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6
|
Jul 1990 |
BNL-NCS-44945 |
| ENDF-102 1991 |
X |
P.F.Rose, C.L.Dunford |
Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6
|
Oct 1991 |
BNL-NCS-44945 REV |
| ENDF-102 1995 |
X |
V.McLane, C.L.Dunford, P.F.Rose |
Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6
|
Nov 1995 |
BNL-NCS-44945 REV.11/95 |
| ENDF-102 1997 |
X |
V.McLane, C.L.Dunford, P.F.Rose |
Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6
|
Feb 1997 |
BNL-NCS-44945 REV.2/97 |
|
ENDF-102 Rev. 2001 |
X |
V.McLane, Ed. |
ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File
ENDF-6 |
Apr 2001 |
BNL-NCS-44945-01/04-Rev. |
| ENDF-103 |
X |
W.A.Wittkopf, D.H.Roy, A.Z.Livolsi |
U-238 Neutron Cross-Section Data for the ENDF/B |
May 1967 |
BAW-316 |
| ENDF-104 |
|
W.A.Wittkopf |
Th-232 Neutron Cross Section Data for the ENDF/B |
|
|
| ENDF-105 |
X |
R.S.Hubner, B.J.Lemke |
EDIT-A Fortran IV level H Program to Punch, Print, and Plot Selected
Portions of an ENDF/B Data Tape |
Nov 1967 |
NAA-SR-12525 |
| ENDF-106 |
X |
C.L.Dunford, R.F.Berland, R.J.Creasy |
SCORE - An Automated Cross Section Evaluation System |
Jan 1968 |
NAA-SR-MEMO-12529 |
| ENDF-107 |
|
Void-Not Used |
|
|
|
| ENDF-108 |
|
M.K.Drake |
Handwritten Notes of Be, U-234, U-236, Pu-241 for ENDF/B |
|
|
| ENDF-109 |
X |
D.C.Irving |
Evaluation of Neutron Cross Sections for Boron-10 |
Oct 1967 |
ORNL/TM-1872 |
| ENDF-110 |
X |
O.Ozer |
Description of the ENDF/B Processing Codes and Retrieval Subroutines |
Jun 1971 |
BNL-50300 |
| ENDF-111 |
X |
D.J.Dudziak |
ENDF/B Format Requirements for Shielding Applications |
Apr 1967 |
LA-3801 |
| ENDF-112 |
X |
J.T.Reynolds, C.R.Lubitz |
Evaluated Cross Sections for the Hafnium Isotopes |
Aug 1967 |
KAPL-3327 (Restrict) |
| ENDF-113 |
X |
R.A.Dannels, D.E.Kusner |
ETOM-1-A Fortran IV Program to Process Data from the ENDF/B File to the
MUFT Format |
May 1968 |
WCAP-3688-1 |
| ENDF-114 |
X |
D.E.Kusner, S.Kellman |
ETOG-1-A Fortran IV Program to Process Data from the ENDF/B File to the
MUFT, GAM and ANISN Formats |
Dec 1969 |
WCAP-3845-1 |
| ENDF-114 Suppl. |
X |
M.Raymund |
ETOG-1-A Fortran IV Program to Process Data from the ENDF/B File to the
MUFT, GAM and ANISN Formats |
Aug 1973 |
WCAP-3845-1 Suppl.1 |
| ENDF-115 |
|
W.B.Henderson |
Evaluation of Re-185 and Re-187 Neutron Cross Sections for ENDF/B |
Mar 1968 |
GEMP-587 |
| ENDF-116 |
X |
J.R.Smith, R.A.Grimesey |
An Evaluation and Compilation of Np-237 Cross Section Data for the
ENDF/B File |
May 1969 |
IN-1182 |
| ENDF-117 |
|
J.R.Smith |
Subject:Am-241,Am-243 |
|
|
| ENDF-118 |
|
Void See ENDF-133 |
|
|
|
| ENDF-119 |
|
Void See ENDF-133 |
|
|
|
| ENDF-120 |
X |
D.M.Green, T.A.Pitterle |
ETOE-A Program for ENDF/B to MC2 Data Conversion |
Jun 1968 |
APDA-219 |
| ENDF-121 |
X |
T.A.Pitterle |
Evaluated Neutron Cross Sections of Sodium-23 for the ENDF/B File |
Jun 1968 |
APDA-217 |
| ENDF-122 |
X |
T.A.Pitterle, M.Yamamoto |
Evaluated Neutron Cross Sections of Pu-240 for the ENDF/B File |
Jun 1968 |
APDA-218 |
| ENDF-123 |
X |
J.T.Reynolds |
Evaluated Neutron Cross Sections for the Gadolinium Isotopes |
May 1968 |
KAPL-3416 (Restrict) |
| ENDF-124 |
X |
J.M.Otter, R.S.Hubner, R.W.Campbell, et al. |
Evaluated Neutron Cross Sections for Cu-63, Cu-65, and Natural Cu |
Dec 1968 |
AI-AEC-12741 |
| ENDF-125 |
X |
E.M.Pennington |
ENDF/B Neutron Cross Section Data for Natural Helium |
Oct 1968 |
ANL-7462 |
| ENDF-126 |
X |
C.L.Dunford ,R.F.Berland, R.S.Hubner, R.J.Creasy |
SCORE II-An Interactive Neutron Evaluation System |
Mar 1969 |
AI-AEC-12757 |
| ENDF-127 |
|
R.E.Schenter |
ETOX-A. Code to Calculate Group Constants for Nuclear Reactor
Calculations |
May 1969 |
BNWL-1002 |
| ENDF-128 |
X |
D.J.Dudziak, J.M.Cook |
LUTE and LATEX, Special-Purpose Codes to Translate from Modified UK to
ENDF/B Format |
Aug 1969 |
NE-3383-102-69U |
| ENDF-129 |
|
N.Azziz |
Iron, Nickel, and Chromium Neutron Cross Sections from 0-15 MeV |
Aug 1969 |
WCAP-7281 |
| ENDF-130 |
X |
D.J.Dudziak |
Translation to ENDF/B and "Physics" Checking of Cross Sections for
Shielding |
Nov 1969 |
DASA-2379 |
| ENDF-131 |
|
N.M.Green |
An Evaluation and Compilation of the Fission and Capture Cross Sections
of... |
Feb 1970 |
ORNL/TM-2797 |
| ENDF-132 |
X |
D.J.Dudziak, A.H.Marshall, R.E.Seamon |
LAPH: A Multigroup Photon Production Matrix and Source Vector Code for
ENDF/B |
May 1970 |
LA-4337 |
| ENDF-133 |
|
S.Kellman |
Description of the Generation of Data Decks by ETOG-1 for Use in Creating
... |
Jan 1970 |
WCAP-3845-2 |
| ENDF-134 |
|
R.Q.Wright, S.N.Cramer, D.C.Irving |
UKE-III: A Computer Program for Translating Neutron Cross Section ...
|
Mar 1970 |
ORNL-TM-2880 |
| ENDF-134R |
X |
R.Q.Wright, S.N.Cramer, D.C.Irving |
UKE-III: A Computer Program for Translating Neutron Cross Section Data
From the UKAEA Nuclear Data Library ... |
Oct 1973 |
ORNL-TM-2880 REV |
| ENDF-135 |
|
J.T.Reynolds |
Evaluated Neutron Cross Sections for the Zirconium Isotopes |
Mar 1970 |
KAPL-M-7078 (Restrict) |
| ENDF-136 |
X |
T.A.Pitterle |
Evaluation of U-238 Neutron Cross Sections for the ENDF/B Version II
File |
Mar 1971 |
WARD-4181-1 |
| ENDF-137 |
|
D.C.Irving |
LEGCK: A Subroutine to Analyze Legendre Coefficients for Negativity in
the... |
Sep 1970 |
ORNL/TM-2903 |
| ENDF-138 |
|
D.C.Irving |
Evaluation of the Cross Sections of Iron:ENDF/B MAT 1101 |
Sep 1970 |
ORNL/TM-2891 |
| ENDF-139 |
|
S.K.Penny |
A Re-Evaluation of Natural Iron Neutron and Gamma-Ray Production Cross
... |
Apr 1971 |
ORNL-4617 |
| ENDF-140 |
X |
D.J.Dudziak |
PHOXE: A Fortran-IV Code to Check Format Syntax, Consistency, and
Physical Realism of ENDF/B Photon Production Data |
Sep 1970 |
LA-4506-MS |
| ENDF-141 |
|
L.Stewart |
Evaluated Nuclear Data for Hydrogen in the ENDF/B-II Format |
Feb 1971 |
LA-4574 |
| ENDF-142 |
X |
C.L.Thompson, J.R.Stockton, L.M.Petrie, et al. |
EDITOR, A Processing code for ENDF/B Format Data |
Feb 1971 |
ORNL-TM-3266 |
| ENDF-143 |
X |
R.B.Kidman, R.E.Schenter |
Group Constants for Fast Reactor Calculations |
Mar 1971 |
HEDL-TME-71-36 |
| ENDF-144 |
X |
A.Z.Livolsi |
Evaluation of Tc-99 and Rh-103 Neutron Cross Sections for ENDF/B-III |
Nov 1971 |
BAW-1367 |
| ENDF-145 |
X |
B.A.Hutchins, C.L.Cowen, M.D.Kelley, J.E.Turner |
ENDRUN-II: A Computer Code to Generate a Generalized Multigroup Data
File from ENDF/B |
Mar 1971 |
GEAP-13704 |
| ENDF-146 |
X |
C.L.Beard, R.A.Dannels |
ETOT: A Fortran IV Program to Process Data from the ENDF/B File to
Thermal Library Format |
Mar 1971 |
WCAP-7363 |
| ENDF-146 Suppl. |
X |
M.Raymund |
ETOT, A Fortran-IV Program to Process Data from the ENDF/B File to
Thermal Library Format |
Nov 1973 |
WCAP-7363 |
| ENDF-147 |
X |
H.Alter, R.S.Hubner |
Status of Fast Neutron Cross Section Data Testing using ENDF/B-II Data
Files |
May 1971 |
AI-AEC-12999 |
| ENDF-148 |
X |
M.R.Bhat |
ENDF/B Processing Codes for the Resonance Region |
Jun 1971 |
BNL-50296 |
| ENDF-149 |
|
H.Alter |
Evaluation of Several ENDF/B-II Cross-Section Sets Using Monte Carlo...
|
Jun 1971 |
AI-AEC-13001 |
| ENDF-150 |
X |
E.H.Ottewitte, J.M.Otter, P.F.Rose, C.L.Dunford |
An Evaluation of Ta-181 and Ta-182 for the ENDF/B Data File |
Sep 1971 |
AI-AEC-12990 |
| ENDF-151 |
|
R.W.Roussin |
Preparation of Data Sets in ENDF Format for Na, Mg, Cl, and K for Use in
... |
May 1971 |
ORNL/TM-3429 |
| ENDF-152 |
X |
H.C.Honeck, D.R.Finch |
FLANGE II(Version 71-1). A Code to Process Thermal Neutron Data from an
ENDF/B tape |
Oct 1971 |
DP-1278 |
| ENDF-153 |
X |
B.R.Leonard Jr. |
Thermal Cross Sections of the Fissile and Fertile Nuclei for ENDF/B-II
|
Jun 1971 |
BNWL-1586 |
| ENDF-154 |
|
Void-Not Used |
|
|
|
| ENDF-155 |
X |
D.J.Dudziak, J.M.Romero |
VIXEN: A Code to Check Physical Consistency of Photon-Production Data in
Rived ENDF Format |
Oct 1971 |
LA-4739 |
| ENDF-156 |
|
D.J.Dudziak |
LAPHANO: P0 Multigroup Photon Production Matrix and Source Code for ENDF
|
Jan 1972 |
LA-4750-MS |
| ENDF-157 |
|
M.Raymund |
Subject:PSYCHE Code |
|
|
| ENDF-158 |
X |
F.J.McCrosson, D.R.Finch, E.C.Olson |
Testing of ENDF/B-Thermos Cross Sections for H2O, D2O, C, ZrH2, (C2H4)x,
Be, Be0, C6H6, and U02 |
Oct 1971 |
DP-1276 |
| ENDF-159 |
|
R.E.Schenter |
Cross Section Evaluations of Twenty-Seven Fission Product Isotopes for...
|
Oct 1971 |
HEDL-TME-71-143 |
| ENDF-160 |
X |
A.D.MacKellar, R.E.Schenter |
Optical Model Studies for Fast Neutron Capture Cross Section Calculations
|
Aug 1972 |
HEDL-TME-71-154 |
| ENDF-161 |
X |
J.R.Smith, R.C.Young |
U-235 Resolved Resonance Parameters for ENDF/B-III |
Dec 1971 |
ANCR-1044 |
| ENDF-162 |
X |
O.D.Simpson, F.B.Simpson |
Evaluation of the Pu-239 Cross Sections in the Resonance Region for the
ENDF/B-III Data File |
Dec 1971 |
ANCR-1045 |
| ENDF-163 |
X |
M.R.Bhat, A.Prince |
Evaluated Neutron Cross Sections for Ag-107, Ag-109 and Cs-133 |
Apr 1973 |
BNL-50383 |
| ENDF-164 |
|
R.E.Schenter |
FTR Set 300,Multigroup Cross Sections for FTR Design |
Oct 1971 |
HEDL-TME-71-153 |
| ENDF-165 |
|
Void-Not Used |
|
|
|
| ENDF-166 |
|
R.E.Maerker |
SDT1. Iron Broomstick Experiment |
Jul 1972 |
ORNL/TM-3867 |
| ENDF-167 |
|
R.E.Maerker |
SDT2. Oxygen Broomstick Experiment |
Jul 1972 |
ORNL/TM-3868 |
| ENDF-168 |
|
R.E.Maerker |
SDT3. Nitrogen Broomstick Experiment |
Jul 1972 |
ORNL/TM-3869 |
| ENDF-169 |
|
R.E.Maerker |
SDT4. Sodium Broomstick Experiment |
Jul 1972 |
ORNL/TM-3870 |
| ENDF-170 |
|
R.E.Maerker |
SDT5. Stainless-Steel Broomstick Experiment |
Jul 1972 |
ORNL/TM-3871 |
| ENDF-171 |
|
F.Schmittroth |
Neutron Resonance Spacings for Spherical Nuclei |
Jan 1973 |
HEDL-TME-73-30 |
| ENDF-172 |
X |
W.E.Ford III |
Comparison of (n th,gamma) Yields from the Current ENDF/B-III Data with
Published Data |
Aug 1972 |
ORNL-TM-3910 |
| ENDF-173 |
|
P.G.Young |
Evaluation of the Neutron and Gamma Ray Production Cross Sections for
Nitrogen |
Sep 1972 |
LA-4725 |
| ENDF-174 |
|
D.G.Foster |
A Preliminary Evaluation of the Neutron and Photon Production Cross...
|
Aug 1972 |
LA-4780 |
| ENDF-175 |
|
P.G.Young |
A Preliminary Evaluation of the Neutron and Photon-Production Cross...
|
Dec 1972 |
LA-4726 |
| ENDF-176 |
|
R.E.Maerker |
SDT6. Experiment on Secondary Gamma-Ray Production Cross Sections Arising
... |
Oct 1972 |
ORNL/TM-3957 |
| ENDF-177 |
|
R.E.Maerker |
SDT7. Experiment on Secondary Gamma-ray Production Cross Sections Arising
... |
Oct 1972 |
ORNL/TM-3974 |
| ENDF-178 |
|
F.G.Perey |
A Test of Neutron Total Cross Section Evaluations from 0.2 to 20 MeV for
... |
Dec 1972 |
ORNL-4823 |
| ENDF-179 |
X |
M.K.Drake |
ENDF/B-III Cross Section Measurement Standards |
Jul 1972 |
BNL-17188 |
| ENDF-180 |
X |
W.E.Ford III |
The Testing of Photon Production Data from ENDF/B-III Material 1135(Al)
|
Jan 1973 |
ORNL-TM-4032 |
| ENDF-181 |
|
P.F.Rose, H.Alter, R.K.Paschall, A.W.Thiele |
SDT9. CSEWG Shielding Benchmark Specifications Neutron Attenuation
Measurements in a Mockup of the FFTF Radial Shield |
Jan 1973 |
AI-AEC-13048 |
| ENDF-182 |
X |
D.J.Dudziak, G.E.Bosler |
LAPHAN: A Code to Compute the P0 to P4 Multigroup Photon-Production
Matrices |
Jan 1973 |
LA-4963 |
| ENDF-183 |
X |
H.Alter |
Report to the Cross Section Evaluation Working Group GEDANKEN Calculations
|
Nov 1972 |
BNL-17510 |
| ENDF-184 |
|
R.Q.Wright |
A Comparison of the Group Constants Generated by the ENDF/B Processing
... |
Apr 1973 |
ORNL/TM-4041 |
| ENDF-185 |
X |
M.R.Bhat, S.F.Mughabghab |
Evaluated Neutron Cross Sections for the Stable Isotopes of Xenon |
Feb 1973 |
BNL-50374 |
| ENDF-186 |
X |
M.R.Bhat, M.D.Goldberg, R.R.Kinsey, et al. |
Neutron and Gamma Ray Production Cross Sections for Silicon |
Mar 1973 |
BNL-50379 |
| ENDF-187 |
X |
M.R.Bhat |
Multi-Level Effects in Reactor Calculations and the Probability Table
Method |
Apr 1973 |
BNL-50387 |
| ENDF-188 |
X |
R.E.Maerker |
SDT11. The ORNL Benchmark Experiment for Neutron Transport Through Iron
and Stainless Steel, Part 1 |
Sep 1974 |
ORNL-TM-4222 |
| ENDF-189 |
X |
R.E.Maerker |
SDT12. The ORNL Benchmark Experiment for Neutron Transport Through
Sodium |
Sep 1974 |
ORNL-TM-4223 |
| ENDF-190 |
X |
A.Prince, M.K.Drake, P.Hlavac |
An Analysis of the Pu-239 Neutron Cross Sections from 20 keV to 20 MeV
|
Apr 1973 |
BNL-50388 |
| ENDF-191 |
X |
R.Q.Wright |
ADLER-III: A Program to Calculate Cross Sections from Adler-Adler
Resonance Parameters |
Jun 1973 |
ORNL-TM-4257 |
| ENDF-192 |
|
C.R.Weisbin |
Specification of a Generally Useful Multigroup Structure for Neutron
Transpor |
May 1973 |
LA-5277 |
| ENDF-193 |
|
Void-Not Used |
|
|
|
| ENDF-194 |
X |
F.Schmittroth, R.E.Schenter |
Fast Neutron Capture Cross Section for Fission Product Isotopes |
Aug 1973 |
HEDL-TME-73-63 |
| ENDF-195 |
X |
F.Schmittroth |
Neutron Capture Calculations for En=100 keV to 4 MeV |
Nov 1973 |
HEDL-TME-73-79 |
| ENDF-196 |
X |
D.R.Finch |
Standard Thermal Energy Group Structure for Generation of Thermal Group
Constants from ENDF/B Data |
Mar 1974 |
DP-1346 |
| ENDF-197 |
|
W.E.Kinney |
Natural Nickel and Ni-60 Neutron Elastic and Inelastic Scattering Cross
... |
Jan 1974 |
ORNL-4807 |
| ENDF-198 |
|
W.E.Kinney |
Natural Chromium and Cr-52 Neutron Elastic and Inelastic Scattering Cross
... |
Jan 1974 |
ORNL-4806 |
| ENDF-199 |
|
B.Hutchins |
Subject: Pu-239 |
|
|
| ENDF-200 |
X |
D.E.Cullen, P.J.Hlavac |
ENDF/B Cross Sections |
Nov 1972 |
BNL-17100 |
| ENDF-200 2nd Edition |
X |
D.I.Garber, C.Brewster |
ENDF/B Cross Sections |
Oct 1975 |
BNL-17100 2nd Ed. |
| ENDF-201 1973 |
|
O.Ozer |
ENDF/B Summary Documentation |
May 1973 |
BNL-NCS-17541 1st Ed. |
| ENDF-201 1975 |
|
D.I.Garber |
ENDF/B Summary Documentation |
Oct 1975 |
BNL-NCS-17541 2nd Ed. |
| ENDF-201 1979 |
|
R.R.Kinsey |
ENDF/B Summary Documentation |
Jul 1979 |
BNL-NCS-17541 3rd Ed. |
| ENDF-201 1985 |
|
B.A.Magurno |
ENDF/B-V.2 Summary Documentation |
Jan 1985 |
BNL-NCS-17541 3rd Ed. Suppl.1 |
| ENDF-201 4th Ed. |
X |
P.F.Rose |
ENDF/B-VI Summary Documentation |
Oct 1991 |
BNL-NCS-17541 4th Ed. |
|
ENDF-201 4th Ed. Suppl.1 |
X |
V.McLane |
ENDF/B-VI Summary Documentation Supplement 1,ENDF/HE-VI Summary
Documentation |
Dec 1996 |
BNL-NCS-17541 4th Ed. Suppl.1 |
| ENDF-202 1974 |
X |
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
Nov 1974 |
BNL-19302 |
| ENDF-202 1975 |
|
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
May 1975 |
BNL-19302 Upd. 5/75 |
| ENDF-202 1976 |
|
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
Oct 1976 |
BNL-19302 Upd. 10/76 |
| ENDF-202 1978-1 |
|
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
Feb 1978 |
BNL-19302 Upd. 2/78 |
| ENDF-202 1978-2 |
|
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
Oct 1978 |
BNL-19302 Upd. 10/78 |
| ENDF-202 1981-1 |
|
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
May 1981 |
BNL-19302 Upd. 5/81 |
| ENDF-202 1981-2 |
|
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
Nov 1981 |
BNL-19302 Upd.11/81 |
| ENDF-202 1982 |
|
H.Alter |
Cross Sections Evaluation Working Group Benchmark Specification |
Sep 1982 |
BNL-19302 Upd. 9/82 |
| ENDF-202 1983 Vol.2 |
|
P.F.Rose |
Cross Sections Evaluation Working Group Benchmark Specifications |
Dec 1983 |
BNL-19302 Vol.2 |
| ENDF-202 1983 Vol.2 Suppl. |
X |
P.F.Rose |
Cross Section Evaluation Working Group Benchmark Specifications |
Sep 1986 |
BNL-19302 Vol.2 Suppl. |
| ENDF-202 1991 |
|
R.McKnight |
Cross Sections Evaluation Working Group Benchmark Specification |
Sep 1991 |
BNL-19302 Upd. 9/91 |
| ENDF-203 |
|
W.E.Kinney |
Fe-54 Neutron Elastic and Inelastic Scattering Cross Sections from 5.50
... |
Mar 1974 |
ORNL-4907 |
| ENDF-204 |
|
W.E.Kinney |
Cu-63 and Cu-65 Neutron Elastic and Inelastic Scattering Cross Sections
... |
Mar 1974 |
ORNL-4908 |
| ENDF-205 |
|
F.G.Perey |
Nitrogen Neutron Elastic and Inelastic Scattering Cross Sections from
4.34... |
Mar 1974 |
ORNL-4905 |
| ENDF-206 |
|
W.E.Kinney |
Pb-206, Pb-207, and Pb-208 Neutron Elastic and Inelastic Scattering Cross
... |
Jun 1974 |
ORNL-4909 |
| ENDF-207 |
X |
M.R.Bhat |
Neutron and Gamma-Ray Production Cross Sections for Nickel |
Oct 1974 |
BNL-50435 |
| ENDF-208 |
X |
H.Takahashi |
Evaluation of the Neutron and Gamma-Ray Production Cross Sections for
55Mn |
Nov 1974 |
BNL-50442 |
| ENDF-209 |
|
Void See ENDF-246 |
|
|
|
| ENDF-210 |
X |
C.W.Reich, R.G.Helmer, M.H.Putnam |
Radioactive-Nuclide Decay Data for ENDF/B |
Aug 1974 |
ANCR-1157 |
| ENDF-211 |
|
Void-Not Used |
|
|
|
| ENDF-212 |
X |
M.R.Bhat, B.A.Magurno, S.Pearlstein, F.M.Scheffel |
Nuclear Data for CTR Related Projects |
Oct 1974 |
BNL-19344 |
| ENDF-213 |
X |
H.Takahashi |
Evaluation of the Neutron and Gamma-Ray Production Cross Sections of
Eu-151 and Eu-153 |
Nov 1974 |
BNL-19455 |
| ENDF-214 |
X |
H.Takahashi |
Evaluation of the Neutron Cross Sections for Eu-152 and Eu-154 |
Nov 1974 |
BNL-19456 |
| ENDF-215 |
X |
S.F.Mughabghab, A.Prince, M.D.Goldberg, et al. |
Evaluated Neutron Cross Sections of Au-197 |
Oct 1974 |
BNL-50439 |
| ENDF-216 |
X |
B.A.Magurno |
ENDF/B-IV Dosimetry File |
Apr 1975 |
BNL-NCS-50446 |
| ENDF-217 |
X |
S.Pearlstein |
Seminar on 238-U Resonance Capture |
Mar 1975 |
BNL-NCS-50451 |
| ENDF-218 |
X |
C.R.Weisbin, E.M.Oblow, J.Ching, et al. |
Cross Section and Method Uncertainties:the Application of Sensitivity
Analysis ... |
Aug 1975 |
ORNL-TM-4847 |
| ENDF-219 |
X |
J.K.Dickens, G.L.Morgan, E.Newman |
The Nb(n,x gamma) Reaction Cross Section for Incident Neutron Energies
Between 0.65 and 20.0 MeV |
Sep 1975 |
ORNL-TM-4972 |
| ENDF-220 |
X |
G.L.Morgan, E.Newman |
The Mo(n,x gamma) Reaction Cross Section for Incident Neutron Energies
Between 0.2 and 20.0 MeV |
Dec 1975 |
ORNL-TM-5097 |
| ENDF-221 |
|
E.Newman |
V(n,x gamma) Reaction Cross Section for Incident Neutron Energies... |
Apr 1976 |
ORNL/TM-5299 |
| ENDF-222 |
|
G.L.Morgan |
Cr(n,x gamma)Reaction Cross Section for Incident Neutron Energies Between
... |
Jan 1976 |
ORNL/TM-5098 |
| ENDF-223 |
X |
T.R.England, R.E.Schenter |
ENDF/B-IV Fission-Product Files: Summary of Major Nuclide Data |
Oct 1975 |
LA-6116-MS |
| ENDF-224 |
|
C.R.Weisbin |
Specification for Pseudo-Composition-Independent Fine-Group and... |
Dec 1975 |
ORNL/TM-5142 |
| ENDF-225 |
X |
B.A.Magurno |
ENDF/B-IV Cross Section Measurement Standards |
Aug 1975 |
BNL-NCS-50464 |
| ENDF-226 |
|
R.E.Maerker |
Subject: Benchmark |
|
ORNL/TM-5202 |
| ENDF-227 |
X |
R.E.Maerker |
SB2. Experiment on Secondary Gamma-Ray Production Cross Sections Arising
from Thermal-Neutron Capture ... |
Jan 1976 |
ORNL-TM-5203 |
| ENDF-228 |
|
R.E.Maerker |
SB3. Experiment on Secondary Gamma-Ray Production Cross Sections Averaged
... |
Jan 1976 |
ORNL/TM-5204 |
| ENDF-229 |
X |
S.F.Mughabghab, T.J.Krieger |
Neutron Cross Sections of 59Co Below 100 keV |
Apr 1975 |
BNL-NCS-50468 |
| ENDF-230 Vol.I |
X |
E.M.Bohn, R.Maerker, B.A.Magurno, et al. |
Benchmark Testing of ENDF/B-IV |
Mar 1976 |
BNL-NCS-21118 Vol.I |
| ENDF-230 Vol.II |
X |
E.M.Bohn, R.Maerker, B.A.Magurno, et al. |
Benchmark Testing of ENDF/B-IV |
Mar 1976 |
BNL-NCS-21118 Vol.II |
| ENDF-231 |
|
Void See ENDF-265 |
|
|
|
| ENDF-232 |
X |
A.Prince |
Evaluation of Neutron Cross Sections For the Krypton Isotopes |
Aug 1974 |
BNL-NCS-50503 |
| ENDF-233 |
|
R.W.Peelle |
An Evaluation for ENDF/B-IV of the Neutron Cross Sections for U-235
from... |
Jun 1976 |
ORNL-4955 |
| ENDF-234 |
X |
J.H.Marable, J.L.Lucius, C.R.Weibin |
Compilation of Sensitivity Profiles for Several CSEWG Fast Reactor
Benchmarks |
Mar 1977 |
ORNL-5262 |
| ENDF-235 |
X |
J.D.Drischler, C.R.Weisbin |
Compilation of Multigroup Cross-Section Covariance Matrices for Several
Important Reactor Materials |
Oct 1977 |
ORNL-5318 |
| ENDF-236 |
|
C.R.Weisbin |
Application of FORSS Sensitivity and Uncertainty Methodology to Fast
|
Dec 1976 |
ORNL/TM-5563 |
| ENDF-237 |
X |
C.R.Weisbin, P.D.Soran, R.E.MacFarlane, et al. |
MINX: A Multigroup Interpretation of Nuclear X-Sections from ENDF/B |
Sep 1976 |
LA-6486-MS |
| ENDF-238 |
|
R.A.Grimesey |
ETOP 14: A Fortran Code to Process ENDF/B Data into the 68-Group PHROG...
|
Jul 1976 |
ANCR-1322 |
| ENDF-239 |
|
H.Henryson II |
MC2-2: A Code to Calculate Fast Neutron Spectra and Multigroup Cross
Sections |
Jun 1976 |
ANL-8144 |
| ENDF-240 |
X |
D.G.Madland, T.R.England |
The Influence of Pairing on the Distribution of Independent Yield
Strengths in Neutron-induced Fission |
Jul 1976 |
LA-6430-MS |
| ENDF-241 |
X |
D.G.Madland, T.R.England |
Distribution of Independent Fission-Product Yields to Isomeric States |
Nov 1976 |
LA-6595-MS |
| ENDF-242 |
X |
M.Stamatelatos, T.R.England |
Beta-Energy Averaging and Beta Spectra |
Aug 1976 |
LA-6445-MS |
| ENDF-243 Vol.I |
X |
P.F.Rose, T.W.Burrows |
ENDF/B Fission Product Decay Data |
Aug 1976 |
BNL-NCS-50545 Vol.I |
| ENDF-243 Vol.II |
X |
P.F.Rose, T.W.Burrows |
ENDF/B Fission Product Decay Data |
Aug 1976 |
BNL-NCS-50545 Vol.II |
| ENDF-244 |
X |
G.M.Hale, L.Stewart, P.G.Young |
Light Element Standard Cross Standards for ENDF/B-IV |
Oct 1976 |
LA-6518-MS |
| ENDF-245 |
|
F.M.Mann |
HAUSER*4: A Computer Code to Calculate Nuclear Cross Sections |
Sep 1976 |
HEDL-TME-76-80 |
| ENDF-246 |
X |
A.Prince |
Evaluation of Chromium Neutron and Gamma Production Cross Sections for
ENDF/IV |
Aug 1976 |
BNL-NCS-50593 |
| ENDF-247 |
X |
D.G.Madland, L.Stewart |
Light Ternary Fission Products: Probabilities and Charge Distributions
|
Apr 1977 |
LA-6783-MS |
| ENDF-248 |
X |
M.R.Bhat |
Evaluation of 235-U Neutron Cross Section and Gamma Ray Production
Data for ENDF/B-V |
Mar 1980 |
BNL-NCS-51184 |
| ENDF-249 |
|
F.G.Perey |
Data Covariance Files for ENDF/B-V |
Jul 1977 |
ORNL/TM-5938 |
| ENDF-250 |
X |
J.H.Marable, J.D.Drischler, C.R.Weisbin |
SENDIN and SENTINEL: Two Computer Codes to Assess the Effects of
Nuclear Data Changes |
Jul 1977 |
ORNL/TM-5946 |
| ENDF-251 |
|
F.M.Mann |
HEDL Evaluation of Actinide Cross Section for ENDF/B-V |
Jun 1977 |
HEDL-TME-77-54 |
| ENDF-252 |
X |
E.T.Tomlinson, D.deSaussure, C.R.Weisbin |
Sensitivity Analysis of TRX-2 Lattice Parameters with Emphasis on
Epithermal 238-U Capture |
Mar 1977 |
EPRI-NP-346 |
| ENDF-253 |
X |
E.T.Tomlinson, J.L.Lucius, J.D.Drischler |
A Compendium of Energy-Dependent Sensitivity Profiles for TRX-2 Thermal
Lattice |
Mar 1978 |
ORNL-5336 |
| ENDF-254 |
X |
F.G.Perey |
Least-Squares Dosimetry Unfolding: the Program STAY'SL |
Oct 1977 |
ORNL/TM-6062 |
| ENDF-255 |
X |
D.K.Olsen, G.deSaussure, R.B.Perey, et al. |
150-m Measurement of 0.880- to 100.0-keV Neutron Transmissions Through
Four Samples of 238U |
Oct 1977 |
ORNL/TM-5915 |
| ENDF-256 |
X |
J.D.Drischler, J.H.Marable, C.R.Weisbin |
COVERT and CAVALIER: Two Computer Codes for Estimating Uncertainties of
Calculated Neutronics Parameters ... |
Aug 1978 |
ORNL/TM-6078 |
| ENDF-257 |
X |
G.De Saussure, D.K.Olsen, R.B.Perey, F.C.Difilippo |
Evaluation of the U-238 Neutron Cross Sections for Incident Neutron
Energies up to 4Kev |
Jan 1978 |
ORNL/TM-6152 |
| ENDF-258 |
X |
R.E.Maerker, F.J.Muckenthaler, C.E.Clifford |
SB4. Measurements and Calculations of the ORNL CRBR Upper Axial Shield
Experiment |
Jun 1977 |
ORNL-5259 |
| ENDF-259 |
X |
F.G.Perey |
Contributions to Few-Channel Spectrum Unfolding |
Feb 1978 |
ORNL/TM-6267 |
| ENDF-260 |
|
G.De Sauaaure |
Evaluation of the Th-232 Neutron Capture Cross Section above 3 KeV |
Feb 1978 |
ORNL/TM-6161 |
| ENDF-261 |
X |
G.De Saussure, D.K.Olsen, R.B.Perey |
SIOB: A Fortran Code for Least Squares Shape Fitting Several Neutron
Transmission Measurements Using ... |
May 1978 |
ORNL/TM-6286 |
| ENDF-262 |
X |
R.Gwin |
Review and Combination of Experimental Results for Neutron-Emission per
Fission of 232Th |
May 1978 |
ORNL/TM-6245 |
| ENDF-263 |
X |
M.L.Williams, C.R.Weisbin |
Sensitivity and Uncertainity Analysis for Functionals of the
Time-Dependent Nuclide Density Field |
Apr 1978 |
ORNL-5393 |
| ENDF-264 |
X |
R.Gwin, R.R.Spencer, R.W.Ingle, et al. |
Measurements of the Average Number of Prompt Neutrons Emitted per
Fission of 239Pu and 235U |
May 1978 |
ORNL/TM-6246 |
| ENDF-265 |
X |
C.R.Weisbin, J.H.Marable, J.Hardy Jr., R.D.McKnight |
Sensitivity Coefficient Compilation for CSEWG Data Testing Benchmarks
|
Aug 1978 |
BNL-NCS-24853 |
| ENDF-266 |
X |
Y.D.Harker, J.W.Rogers, D.A.Millsap |
Fission Product and Reactor Dosimetry Studies at Coupled Fast Reactivity
Measurements Facility |
Mar 1978 |
TREE-1259 |
| ENDF-267 |
|
C.Y.Fu |
Evaluation for Th-233(n,n')(n,2n) and (n,3n) Cross Section |
May 1978 |
ORNL/TM-6316 |
| ENDF-268 |
X |
M.R.Bhat |
Evaluation of Th-232 for ENDF/B-V |
Feb 1981 |
BNL-NCS-51360 |
| ENDF-269 |
X |
J.U.Koppel, D.H.Houston |
Reference Manual for ENDF Thermal Neutron Scattering Data |
Jul 1978 |
GA-8774 Revised |
| ENDF-270 |
X |
P.F.Rose, S.Pearlstein, O.Ozer |
Symposium Proceedings: Nuclear Data Problems for Thermal Reactor
Applications |
June 1979 |
BNL-NCS-25047 |
| ENDF-271 |
|
F.M.Mann |
HEDL Evaluation of Thorium Cycle Cross Sections for ENDF/B-V |
Nov 1978 |
HEDL-TME-78-100 |
| ENDF-272 |
X |
R.E.MacFarlane, R.J.Barrett, D.W.Muir, R.M.Boicourt |
The NJOY Nuclear Data Processing System: Users Manual |
Dec 1978 |
LA-7584-M |
| ENDF-273 |
X |
G.L.Morgan |
Cross Sections for the Cu(n,xn) and Cu(n,x gamma) Reactions Between 1
and 20 Mev |
Feb 1979 |
ORNL-5499 |
| ENDF-274 |
X |
C.R.Weisbin, R.W.Roussin, J.J.Wagschal, et al. |
VITAMIN-E: An ENDF/B-V Multigroup Cross Section Library for LMFBR Core
and Shield, LWR Shield, ... |
Dec 1978 |
ORNL-5505 |
| ENDF-275 |
X |
J.L.Lucius, E.M.Oblow, G.W.Cunningham,III |
A Users Guide for the JULIET Module of the FORSS Sensitivity and
Uncertainty Analysis Code System |
Feb 1979 |
ORNL/TM-6594 |
| ENDF-276 |
|
C.R.Weisbin |
Specifications for Adjusted Cross Sections and Covariance Libraries
based... |
Feb 1979 |
ORNL-5517 |
| ENDF-277 |
X |
F.C.Difilippo, R.B.Perez, G.deSaussure, et al. |
The U-238 Neutron Induced Fission Cross Section for Incident Neutron
Energies Between 5 eV and 3.5 MeV |
Feb 1979 |
ORNL/TM-6788 |
| ENDF-278 |
X |
L.Stewart |
Summary of Fission Spectrum Workshop Held at NNCSC |
Oct 1978 |
LA-7739-C |
| ENDF-279 |
X |
A.Prince |
ENDF/B-V Neutron Cross Section Evaluation for the Krypton Isotopes |
Jan 1979 |
BNL-NCS-51028 |
| ENDF-280 |
X |
D.M.Hetrick, D.C.Larson, C.Y.Fu |
Status of ENDF/B-V Neutron Emission Spectra Induced by 14 MeV Neutrons
|
Apr 1979 |
ORNL/TM-6637 |
| ENDF-281 |
X |
D.K.Olsen, G.L.Morgan, J.W.McConnell |
Measurement of 238-U(n,n'gamma) and Li-7(n,n'gamma) Gamma-Ray
Production Cross Sections |
May 1979 |
ORNL/TM-6832 |
| ENDF-282 |
X |
G.L.Morgan |
The Th(n,x gamma) Reaction Cross Section for Incident Neutron Energies
Between 0.3 and 20.0 Mev |
Aug 1979 |
ORNL/TM-6758 |
| ENDF-283 |
X |
P.G.Young, L.Stewart |
Evaluated Data for n+Berylium 9 Reactions |
Jul 1979 |
LA-7932-MS |
| ENDF-284 |
X |
G.L.Morgan, G.T.Chapman |
The O(n,x gamma) Reaction Cross Section for Incident Neutron Energies
Between 6.5 and 20.0 MeV |
Sep 1979 |
ORNL-5575 |
| ENDF-285 |
X |
R.R.Spencer, R.Gwin, R.Ingle, H.Weaver |
Interim Report on the ORNL Absolute Measurements of nu p for 252Cf |
Sep 1979 |
ORNL/TM-6805 |
| ENDF-286 |
X |
A.Prince, T.W.Burrows |
Evaluation of Natural Chromium Neutron Cross Sections for ENDF/B-V |
Feb 1979 |
BNL-NCS-51152 |
| ENDF-287 |
X |
W.E.Ford III, C.C.Webster, B.R.Diggs, et al. |
FCXSEC:Multigroup Cross-Section Libraries for Nuclear Fuel Cycle
Shielding Calculations |
May 1980 |
ORNL/TM-7038 |
| ENDF-288 |
X |
R.J.Barrett, W.E.Ford III, Y.Gohar, et al. |
Comparison of Photon-Production Processing Codes LAPHNGAS, MACK-IV, and
NJOY |
Nov 1979 |
LA-8100-MS |
| ENDF-289 |
X |
R.Gwin, R.R.Spencer, R.W.Ingle, et al. |
Measurement of the Average Number of Prompt Neutrons Emitted per Fission
of 235U Relative to 252Cf ... |
Jan 1980 |
ORNL/TM-7148 |
| ENDF-290 |
X |
N.M.Larson, D.K.Olsen |
Preliminary Study of Pseudorandom Binary Sequence Pulsing of ORELA |
Mar 1980 |
ORNL/TM-6632 |
| ENDF-291 #1 |
X |
J.L.Lucius, C.R.Weisbin, J.H.Marable, et al. |
A Users Manual for the FORSS Sensitivity and Uncertainty Analysis Code
System |
Jan 1984 |
ORNL-5316 |
| ENDF-291 #2 |
X |
J.D.Drischler |
The COVERX Service Module of the FORSS System |
Apr 1980 |
ORNL/TM-7181 |
| ENDF-292 |
|
B.F.Rider |
Compilation Efficient Products Yield |
Sep 1980 |
NEDO 12154-3(B) |
| ENDF-293 |
|
T.Burrows |
ENDF/B-V Actinide Decay Data |
|
|
| ENDF-294 |
X |
M.Divadeenam |
Ni Elemental Neutron Induced Reaction Cross Section Evaluation |
Mar 1979 |
BNL-NCS-51346 |
| ENDF-295 |
X |
J.D.Smith III |
Processing ENDF/B-V Uncertainty Data into Multigroup Covariance Matrices
|
Jun 1980 |
ORNL/TM-7221 |
| ENDF-296 |
X |
R.W.Roussin, C.R.Weisbin, J.E.White, et al. |
VITAMIN C: The CTR Processed Multigroup Cross Section Library for
Neutronics Studies |
Jul 1980 |
ORNL/RSIC-37 |
| ENDF-297 |
X |
N.M.Larson, F.G.Perey, J.A.Harvey |
User's Guide for SAMMY: A Computer Model for Multilevel R-Matrix Fits
to Neutron Data Using Bayes' Equstions |
Nov 1980 |
ORNL/TM-7485 |
| ENDF-298 |
X |
C.M.Perey, F.G.Perey |
Evaluation of Resonance Parameters for Neutron Interaction with Iron
Isotopes for Energies up to 400 KeV |
Sep 1980 |
ORNL/TM-6405 |
| ENDF-299 |
X |
D.C.Larson |
An Evaluation Cross Sections for Neutron-Induced Reactions in Sodium |
Sep 1980 |
ORNL-5662 |
| ENDF-300 |
X |
M.R.Bhat |
Standard Reference and Other Important Nuclear Data by the CSEWG |
Dec 1979 |
BNL-NCS-51123 |
| ENDF-300 |
X |
M.R.Bhat |
Standard Reference and Other Important Nuclear Data |
Mar 1981 |
BNL-NCS-51123 5/81 |
| ENDF-300 |
|
M.R.Bhat |
Standard Reference and Other Important Nuclear Data |
Feb 1982 |
BNL-NCS-51123 2/82 |
| ENDF-300 |
X |
M.R.Bhat |
Standard Reference and Other Important Nuclear Data |
May 1984 |
BNL-NCS-51123 5/84 |
| ENDF-301 |
X |
A.D.Carlson, M.R.Bhat |
ENDF/B-V Cross Section Measurement Standards |
Oct 1982 |
BNL-NCS-51619 |
| ENDF-302 |
X |
C.Y.Fu |
Evaluation of Neutron and Gamma-Ray Production Cross Section for
Natural... |
Nov 1980 |
ORNL/TM-7523 |
| ENDF-303 |
X |
D.M.Hetrick, C.Y.Fu |
GLUCS: A Generalized Least-Squares Program for Updating Cross-Section
Evaluations with Correlated Data Sets |
Oct 1980 |
ORNL/TM-7341 |
| ENDF-304 |
X |
E.D.Arthur, P.G.Young |
Evaluated Neutron-Induced Cross Sections for 54 and 56 Fe to 40 MeV |
Dec 1980 |
LA-8626-MS |
| ENDF-305 |
X |
J.D.Smith III, B.L.Broadhead |
Multigroup Covariance Matrices for Fast Reactor Studies |
Apr 1981 |
ORNL/TM-7389 |
| ENDF-306 |
X |
D.W.Muir, R.J.LaBauve |
COVFILS: A 30-Group Covariance Library Based on ENDF/B-V |
Mar 1981 |
LA-8733-MS |
| ENDF-307 |
|
D.K.Olsen |
Measurement of Neutron Transmission Spectra Through 232-Th from 8 meV...
|
Apr 1981 |
ORNL/TM-7661 |
| ENDF-308 |
X |
D.M.Hetrick, C.Y.Fu |
A Calculation of Neutron and Gamma-Ray Production Cross Sections for
Calcium from 8 to 20 MeV |
Jun 1981 |
ORNL/TM-7752 |
| ENDF-309 |
|
J.M.Kallfelz |
Preliminary Analysis and Sensitivity Study of Phenix... |
Sep 1981 |
ORNL/TM-7505 |
| ENDF-310 |
|
J.G.Munoz-Cobos |
PAPIN. A Fortran-IV Program to Calculate Cross Sections Probability...
|
|
|
| ENDF-311 |
X |
C.R.Weisbin, R.D.McKnight, J.Hardy Jr., et al. |
Benchmark Data Testing of ENDF/B-V |
Aug 1982 |
BNL-NCS-31531 |
| ENDF-312 |
X |
G.De Saussure |
Representation of the Neutron Cross Sections of Several Fertile and...
|
Sep 1981 |
ORNL/TM-7945 |
| ENDF-313 |
X |
CSEWG Data Testing Committee |
Benchmark Testing of ENDF/B Data for Thermal Reactors |
Jul 1981 |
BNL-NCS-29891 |
| ENDF-314 |
X |
R.B.Kidman |
ENDF/B-V, LIB-V, CSEWG Benchmarks |
LA-8950-MS |
| ENDF-315 |
X |
R.Gwin, R.R.Spencer,R.W.Ingle |
Measurement of the Average Number of Prompt Neutrons Emitted per Fission
of 233-U Relative to 252-Cf ... |
Nov 1981 |
ORNL/TM-7988 |
| ENDF-316 |
X |
F.M.Mann |
FTR Set 500, A Multigroup Cross-Section Set for FTR Analysis |
Feb 1982 |
HEDL-TME81-31 |
| ENDF-317 |
|
M.A.Bjerke |
Neutron Cross Section Libraries in the MX Master Interface... |
|
|
| ENDF-318 |
|
R.B.Kidman |
Los Alamos Benchmark Calculation Based on ENDF/B-V Data |
|
|
| ENDF-319 |
X |
D.K.Olsen |
An Evaluation of the Resolved-Resonance-Region Cross Sections of 232Th
|
Mar 1982 |
ORNL/TM-8056 |
| ENDF-320 |
X |
R.J.LaBauve, T.R.England, D.C.George |
Integral Data Testing of ENDF/B Fission Product Data and Comparisons of
ENDF/B with other Fission Product Data Files |
Nov 1981 |
LA-9090-MS |
| ENDF-321 |
X |
D.G.Madland |
New Fission Neutron Spectrum Representation for ENDF |
Apr 1982 |
LA-9285-MS |
| ENDF-322 #1 |
X |
T.R.England, W.B.Wilson, R.E.Schenter, F.M.Mann |
Summary of ENDF/B-V Data for Fission Products and Actinides |
Dec 1984 |
EPRI NP 3787 |
| ENDF-322 #2 |
X |
B.F.Rider |
Compilation of Fission Products Yields (Microfiche Only) |
Sept 1980 |
NEDO 12154-3(C) |
| ENDF-323 |
X |
N.M.Larson |
User's Guide for BAYES: A General-Purpose Computer Code for Fitting a
Functional Form to Experimental Data |
Aug 1982 |
ORNL/TM-8185 |
| ENDF-324 Vol.1 |
X |
R.E.MacFarlane, D.W.Muir, R.M.Boicourt |
The NJOY Nuclear Data Processing System, Volume 1: User's Manual |
May 1982 |
LA-9303-M Vol.1 |
| ENDF-324 Vol.2 |
X |
R.E.MacFarlane, D.W.Muir, R.M.Boicourt |
The NJOY Nuclear Data Processing System, Volume II: The NJOY, RECONR,
BROADR, HEATR, AND THERMR Modules |
May 1982 |
LA-9303-M Vol.2 |
| ENDF-324 Vol.3 |
X |
R.E.MacFarlane, D.W.Muir |
The NJOY Nuclear Data Processing System, Volume III: The GROUPR,GAMINR,
and MODER Modules |
Oct 1985 |
LA-9303-M Vol.3 |
| ENDF-324 Vol.4 |
X |
D.W.Muir, R.E.MacFarlane |
The NJOY Nuclear Data Processing System, Volume IV: The ERRORR and
COVR Modules |
Dec 1985 |
LA-9303-M Vol.4 |
| ENDF-325 |
X |
C.Y.Fu |
Summary of ENDF/B-V Evaluations for Carbon,Calcium,Iron,Copper, and Lead
and ENDF/B-V Rev.2 for Calcium and Iron |
Sep 1982 |
ORNL/TM-8283 |
| ENDF-326 |
X |
D.M.Hetrick, C.Y.Fu, D.C.Larson |
Evaluated Neutron-Induced Cross Sections for 40-Ca from 20 to 40 MeV |
Sep 1982 |
ORNL/TM-8290 |
| ENDF-327 |
X |
C.R.Weisbin, D.Gilai, G.deSaussure, R.T.Santoro |
Meeting Cross Section Requirements for Nuclear Energy Design |
Jul 1982 |
ORNL/TM-8220 |
| ENDF-328 |
X |
B.A.Magurno, R.R.Kinsey, F.M.Scheffel |
Guidebook for the ENDF/B-V Nuclear Data Files |
Jul 1982 |
EPRI NP-2510 |
| ENDF-329 |
|
P.F.Rose |
Symposium Proceedings: Thermal Reactor Benchmark Calculation... |
|
|
| ENDF-330 |
X |
C.M.Perey, J.A.Harvey, R.L.Macklin, et al. |
Neutron Transmission and Capture Measurements and Analysis of 60Ni from
1 to 450 Kev |
Nov 1982 |
ORNL-5893 |
| ENDF-331 |
X |
R.W.Peelle, T.W.Burrows |
An Annotated Bibliography Covering Generation and Use of Evalusted
Cross Section Uncertainty Files |
Mar 1983 |
BNL-NCL-51684 |
| ENDF-332 |
|
T.R.England |
ENDF/B-V Summary Data for Fission and Actinides |
|
|
| ENDF-333 |
X |
D.C.Larson, N.M.Larson, J.A.Harvey, et al. |
Application of New Techniques to ORELA Neutron Transmission Measurements
and their Uncertainty Analysis: The Case of Natural Nickel ... |
Oct 1983 |
ORNL/TM-8203 |
| ENDF-334 |
|
D.C.Larson |
ORELA Flight Path 1: Determinations of Its Effective Length vs Energy...
|
Jun 1984 |
ORNL/TM-8880 |
| ENDF-335 |
X |
R.W.Roussin, J.R.Knight, J.H.Hubbell, R.J.Howerton |
Description of the DLC-99/HUGO Package of Photon Interaction Data in
ENDF/B-V Format |
Dec 1983 |
ORNL/RSIC-46 |
| ENDF-336 |
X |
E.D.Arthur, P.G.Young, D.G.Madland, R.E.MacFarlane |
Evaluation of n + 239Pu Nuclear Data for Revision 2 of ENDF/B-V |
Oct 1983 |
LA-9873-MS |
| ENDF-337 |
X |
D.M.Hetrick, C.Y.Fu, D.C.Larson |
Calculated Neutron-Induced Cross Sections for 63,65Cu from 1 to 20 MeV
and Comparisons with Experiments |
Aug 1984 |
ORNL/TM-9083 |
| ENDF-338 |
X |
D.K.Olsen |
Report to the 238U Discrepancy Task Force on SIOB Fitsto the ORNL,CBNM,
and JAERI Transmission Data |
May 1984 |
ORNL/TM-9023 |
| ENDF-339 |
|
N.M.Larson |
Updated Users' Guide for SAMMY: Multilevel R-Matrix Fits to Neutron...
|
Jun 1976 |
ORNL/TM-9179/R1 |
| ENDF-340 |
X |
D.W.Muir |
Analysis of Central Worths and Other Integral Data from the Los Alamos
Benchmark Assemblies |
Oct 1984 |
LA-10230-MS |
| ENDF-341 |
X |
C.Y.Fu, D.M.Hetrick |
Update of ENDF/B-V Mod-3 Iron: Neutron Producting Reaction Cross Sections
and Energy-Angle Correlations |
Jul 1986 |
ORNL/TM-9964 |
| ENDF-342 |
X |
M.S.Milgram, S.Thompson, R.Paulson |
Few Group Cross Sections for 274 Nuclides Based on ENDF/B V |
Feb 1987 |
CRNL-2916 |
| ENDF-343 |
X |
L.W.Weston, E.D.Arthur |
Evaluation of the Neutron Cross Sections for PU-240 |
Apr 1987 |
ORNL/TM-10386 |
| ENDF-344 |
X |
D.M.Hetrick, C.Y.Fu, D.C.Larson |
Calculated Neutron-Induced Cross Sections for 58,60-Ni from 1 to 20 MeV
and Comparisons with Experiments |
Jun 1987 |
ORNL/TM-10219 |
| ENDF-345 |
X |
K.Shibata, D.M.Hetrick |
Calculated Neutron-Induced Cross Sections for 53-Cr from 1 to 20 MeV |
May 1987 |
ORNL/TM-10381 |
| ENDF-346 |
X |
D.M.Hetrick, C.Y.Fu, D.C.Larson |
Calculated Neutron-Induced Cross Sections for 52-Cr from 1 to 20MeV and
Comparisons with Experiments |
Sep 1987 |
ORNL/TM-10417 |
| ENDF-347 |
X |
C.M.Perey, F.G.Perey, J.A.Harvey, et al. |
58Ni+n Transmission, Differential Elastic Scattering and Capture
Measurements and Analysis from 5 to 813 KeV |
Sep 1988 |
ORNL/TM-10841 |
| ENDF-350 |
X |
D.M.Hetrick, D.C.Larson, C.Y.Fu |
Generation of Covariance Files for the Isotopes of Cr, Fe, Ni, Cu, and
Pb in ENDF/B-VI |
Feb 1991 |
ORNL/TM-11763 |
| ENDF-351 |
X |
A.D.Carlson, W.P.Poenitz, G.M.Hale, et al. |
The ENDF/B-VI Neutron Cross Section Measurements Standards |
May 1993 |
NISTIR 5177 |
| ENDF-352 |
X |
J.Katakura, T.R.England |
Augmentation of ENDF/B Fission Product Gamma-Ray Spectra by Calculated
Spectra |
Nov 1991 |
LA-12125-MS |
| ENDF-354 |
X |
L.W.Weston, D.C.Larson |
Compilation of Requests for Nuclear Data |
Jan 1993 |
ORNL/TM-12291 |
| ENDF-355 |
X |
M.C.Moxon |
Comments on the ENDF/B-VI Evaluation for 235-U in the Neutron Energy
Region from 1 to 20 eV |
Feb 1993 |
ORNL/TM-12304 |
| ENDF-358 |
X |
W.P.Poenitz, S.E.Aumeier |
The Simultaneous Evaluation of the Standards and Other Cross Sections of
Importance for Technology |
Sep 1997 |
ANL/NDM-139 |
ENDF-??? |
X |
R.E.Miller, D.L.Smith |
A Compilation of Information on the 32S(p,g)33Cl Reaction and Properties
of Excited Levels in 33CL |
Jul 1997 |
ANL/NDM-143 |
| ENDF-362 |
X |
Soo-Youl Oh, Jonghwa Chang, S. Mughabghab |
Neutron Cross Section Evaluations of Fission Products Below the Fast
Energy Region |
Apr 2000 |
BNL-NCS-67469 |
