B. L. Broadhead

发表

Benchmarking of dose rate calculations for spent fuel transportation casks

B. L. Broadhead, M. C. Brady, C. V. Parks, 1990 .

Computational Methods for Sensitivity and Uncertainty Analysis in Criticality Safety

R. L. Childs, B. L. Broadhead, B. T. Rearden, 1999 .

Sensitivity and uncertainty analysis applied to range of applicability determination

B. L. Broadhead, C. V. Parks, C. M. Hopper, 1999 .

Nuclear data adjustment methodology utilizing resonance parameter sensitivities and uncertainties

B. L. Broadhead, 1984 .

Evaluation of criticality alarm response at the WEMCO Fernald site

R. L. Childs, R. M. Westfall, B. L. Broadhead, 1992 .

Slide Rule for Rapid Response Estimation of Radiological Dose from Criticality Accidents

R. L. Childs, B. L. Broadhead, C. V. Parks, 1999 .

Results for revised biological shield configuration

R. L. Childs, B. L. Broadhead, 1996 .

Criticality Analysis Support for the Three Mile Island Unit 2 Fuel Removal Operations

B. L. Broadhead, C. V. Parks, Robert M. Westfall, 1988 .

Shielding and criticality analyses of phase I reference truck and rail cask designs for spent nuclear fuel

R. L. Childs, B. L. Broadhead, C. V. Parks, 1996 .

K-infinite trends with burnup, enrichment, and cooling time for BWR fuel assemblies

B. L. Broadhead, 1998 .

Guide to verification and validation of the SCALE-4 radiation shielding software

B. L. Broadhead, J. S. Tang, M. B. Emmett, 1996 .

Preliminary assessment of the benefits of derating a cask for increasing age/burnup capability

D. S. Joy, B. L. Broadhead, C. V. Parks, 1992 .

K-Effective Trends with Burnup, Enrichment, and Pooling Time for BWR Fuel Assemblies

B. L. Broadhead, 1998 .

Application of the LEPRICON methodology to the Arkansas Nuclear One, Unit 1 reactor

B. L. Broadhead, B. A. Worley, Mark L Williams, 1986 .

SCAMPI: A code package for cross-section processing

Stephen M. Bowman, N. M. Greene, B. L. Broadhead, 1996 .

Implementation of Surface Detector Option in Scale SAS4 Shielding Module

B. L. Broadhead, M. B. Emmett, J. S. Tang, 1999 .

Development of nuclear analysis capabilities for DOE waste management activities

L. M. Petrie, B. L. Broadhead, C. V. Parks, 1998 .

Generalized Linear Least-Squares Adjustment, Revisited

B. L. Broadhead, J. J. Wagschal, M. L. Williams, 2006 .

EMSP project summary (Project ID: 60077): Development of nuclear analysis capabilities for DOE waste management activities

Bradley T Rearden, B. L. Broadhead, C. M. Hopper, 2000 .

Investigation of Burnup Credit Issues in BWR Fuel

B. L. Broadhead, DeHart, 1999 .

Burnup credit feasibility for BWR spent fuel shipments

B. L. Broadhead, 1990 .

Status of shielding analysis methods for transport packages

B. L. Broadhead, M. C. Brady, C. V. Parks, 1991 .

Scale-4 shipping cask shielding applications

B. L. Broadhead, C. V. Parks, 1991 .

Assessment of shielding analysis methods, codes, and data for spent fuel transport/storage applications. [Radiation dose rates from shielded spent fuels and high-level radioactive waste]

R. W. Roussin, B. L. Kirk, S. N. Cramer, 1988 .

Shielding analyses: the rabbit vs the turtle?

B. L. Broadhead, 1996 .

ORNL contribution to the IAEA bcnchmark problem on fission reactor decommissioning

R. L. Childs, B. L. Broadhead, 1996 .

Nuclear data to support computer code validation

R. T. Primm, B. L. Broadhead, DeHart, 1997 .

SCALE radiation shielding V and V package

B. L. Broadhead, S. M. Bowman, M. B. Emmett, 1997 .

An alternative to the SAS2H/ORIGEN-S sequence to account for water-density effects in BWR systems

B. L. Broadhead, O. W. Hermann, L. C. Leal, 1996 .

Development and application of the automated Monte Carlo biasing procedure in SAS4

B. L. Broadhead, J. S. Tang, B. Broadhead, 1993 .

Verification of criticality accident alarm system for environmental restoration activities

R. L. Childs, B. L. Broadhead, C. M. Hopper, 1995 .

Assessment of proposed dose factor changes to shipping cask design and operation

R. B. Pope, B. L. Broadhead, C. V. Parks, 1992 .

SAS1 and SAS4, two new shielding analysis sequences for spent fuel casks

B. L. Broadhead, C. V. Parks, J. S. Tang, 1991 .

Review of criticality safety and shielding analysis issues for transportation packages

B. L. Broadhead, C. V. Parks, 1995 .

Proposed Methodology for Establishing Area of Applicability

B. L. Broadhead, C. M. Hopper, C. V. Parks, 1999 .

Application of Covariance Data to Criticality Safety Data Validation

B. L. Broadhead, C. V. Parks, C. M. Hopper, 1999 .

Approximate Techniques for Representing Nuclear Data Uncertainties

Bradley T Rearden, B. L. Broadhead, Michael E Dunn, 2007 .

Shielding benchmark calculations of selected spent fuel storage cask experiments

B. L. Broadhead, C. V. Parks, J. S. Tang, 1993 .

An updated nuclear criticality slide rule

B. L. Broadhead, C. M. Hopper, 1998 .

Development of nuclear analysis capabilities for DOE waste management activities. 1998 annual progress report

B. L. Broadhead, C. M. Hopper, DeHart, 1998 .

Shielding calculations for transport casks)

B. L. Broadhead, C. V. Parks, 1990 .

Application of generalized linear least-squares methodology to criticality safety computations

B. L. Broadhead, 1997 .

Evaluation of shielding analysis methods in spent-fuel cask environments

R. L. Childs, B. L. Broadhead, C. V. Parks, 1997 .

Investigation of nuclide importance to functional requirements related to transport and long-term storage of LWR spent fuel

B. L. Broadhead, C. V. Parks, DeHart, 1995 .

Sensitivity/Uncertainty Analysis for Free-in-Air Tissue Kerma Due to Initial Radiation at Hiroshima and Nagasaki

B. L. Broadhead, D. G. Cacuci, J. V. Pace, 1988 .