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R.Q. Wright
Observed names:
R Wright,
R. Q. WRIGHT,
R. Q. Wright,
R. Wright,
RQ Wright,
Richard Q. Wright,
Wright, R. Q.,
Wright, R.Q.
show all 8
Institution:
Oak Ridge National Laboratory
Observed institutions:
Argonne National Laboratory,
Oak Ridge National Laboratory,
Georgia Institute of Technology,
United States Department of Energy,
United States Department of Commerce,
Union Carbide (United States)
show all 6
OpenAlex ID:
A5113433476
ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data
2018
·
D.A. Brown
, M.B. Chadwick
, et al.
·
Nuclear Data Sheets
·
2,525
PDF
AMPX: a modular code system for generating coupled multigroup neutron-gamma libraries from ENDF/B
1976
·
N. M. Greene
, J. L. Lucius
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
115
ENDF/B-VIII.1: Updated Nuclear Reaction Data Library for Science and Applications
2026
·
G.P.A. Nobre
, R. Capote
, et al.
·
Nuclear Data Sheets
·
64
R-Matrix Analysis of235U Neutron Transmission and Cross-Section Measurements in the 0- to 2.25-keV Energy Range
1999
·
L. C. Leal
, H. Derrien
, et al.
·
Nuclear Science and Engineering
·
36
Sensitivity Analysis Using Computer Calculus: A Nuclear Waste Isolation Application
1986
·
E. M. Oblow
, F. G. Pin
, et al.
·
Nuclear Science and Engineering
·
30
SUPERTOG: A PROGRAM TO GENERATE FINE GROUP CONSTANTS AND Pn SCATTERING MATRICES FROM ENDF/B,
1969
·
R.Q. Wright
, N.M. Greene
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
27
VITAMIN-E: an ENDF/B-V multigroup cross-section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology
1979
·
C.R. Weisbin
, R.W. Roussin
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
24
PDF
Production and testing of the VITAMIN-B6 fine group and the BUGLE-93 broad-group neutron/photon cross-section libraries derived from ENDF/B-VI nuclear data
1995
·
Nuclear Regulatory Commission, Washington, DC (United States)
, D Ingersoll
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
19
Vitamin-B6: A fine-group cross section library based on ENDF/B-VI for radiation transport applications
1994
·
J. E. White
, R.Q. Wright
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
18
Transport calculations of neutron transmission through steel using ENDF/B-V, revised ENDF/B-V and ENDF/B-VI iron evaluations
1991
·
M.L. Williams
, C. Aboughantous
, et al.
·
Annals of Nuclear Energy
·
16
R-Matrix Evaluation of16O Neutron Cross Sections up to 6.3 MeV
2002
·
R.O. Sayer
, L.C. Leal
, et al.
·
Journal of Nuclear Science and Technology
·
15
PDF
Users manual for the FORSS sensitivity and uncertainty analysis code system
1981
·
J.L. Lucius
, C.R. Weisbin
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
15
PDF
Automated sensitivity analysis of an atmospheric dispersion model
1992
·
J.E. Horwedel
, R.J. Raridon
, et al.
·
Atmospheric Environment Part A General Topics
·
11
MACK-IV, a new version of MACK: a program to calculate nuclear response functions from data in ENDF/B format
1978
·
M.A. Abdou
, Y. Gohar
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
11
PDF
Use of Metal/Uranium Mixtures to Explore Data Uncertainties
1995
·
Parks, C. V.
, Jordan, W. C.
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
8
PDF
Fission product evaluations for ENDF/B-VI
1990
·
R.Q. Wright
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
8
PDF
ANSL-V: ENDF/B-V based multigroup cross-section libraries for Advanced Neutron Source (ANS) reactor studies
1987
·
William E. Ford
, J.W. Arwood
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
8
An automated sensitivity analysis procedure for the performance assessment of nuclear waste isolation systems
1986
·
F.G. Pin
, B.A. Worley
, et al.
·
Nuclear and Chemical Waste Management
·
7
XLACS A Program to Produce Weighted Multigroup Neutron Cross Sections from ENDF/B
1973
·
N. M. Greene
, J. L. Lucius
, et al.
·
Nuclear Science and Engineering
·
7
Application of an Automated Procedure for Adding a Comprehensive Sensitivity Calculation Capability to the ORIGEN2 Point Depletion and Radioactive Decay Code
1986
·
B. A. Worley
, R. Q. Wright
, et al.
·
Nuclear Science and Engineering
·
6
Validation of SCALE-4 Criticality Sequences Using ENDF/B-V Data
1993
·
Stephen M. Bowman
, R.Q. Wright
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
5
PDF
Sensitivity analysis of EQ3
1990
·
J. E. Horwedel
, R. Q. Wright
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
5
PDF
Specification for pseudo-composition-independent fine-group and composition- dependent fine- and broad-group LMFBR neutron-gamma libraries at ORNL
1975
·
C Weisbin
, R Roussin
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
5
PDF
Calculation of the Minimum Critical Mass of Fissile Nuclides
2008
·
Richard Q. Wright
, Calvin M. Hopper
·
Nuclear Science and Engineering
·
4
Recent Validation Experience with Multigroup Cross-Section Libraries and SCALE
1995
·
Stephen M. Bowman
, R.Q. Wright
, et al.
·
University of North Texas Digital Library (University of North Texas)
·
4
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Works count:
95
Citation count:
3,049
H-index:
12
I10-index:
14
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