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SCALE: A modular code system for performing standardized computer analyses for licensing evaluation
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inferred← citeshttps://doi.org/10.2172/5770065openalex-snapshot
Advanced Neutron Source (ANS) Project Progress report, FY 1991
inferred← citeshttps://doi.org/10.2172/6172319openalex-snapshot
Methods of calculating the post-closure performance of high-level waste repositories
inferred← citeshttps://doi.org/10.2172/6199849openalex-snapshot
Recriticality in a BWR (boiling water reactor) following a core damage event
inferred← citeshttps://doi.org/10.2172/6218812openalex-snapshot
Comparison of radiation spectra from selected source-term computer codes
inferred← citeshttps://doi.org/10.2172/6316472openalex-snapshot
Effect of boron and gadolinium concentration on the calculated neutron multiplication factor of U(3)O/sub 2/ fuel pins in optimum geometries
inferred← citeshttps://doi.org/10.2172/6591225openalex-snapshot
Scoping design analyses for optimized shipping casks containing 1-, 2-, 3-, 5-, 7-, or 10-year-old PWR spent fuel
inferred← citeshttps://doi.org/10.2172/6667910openalex-snapshot
Criticality safety studies for the storage of waste from nuclear fuel service in Intercell Storage Wells 2 and 3 of Building 3019
inferred← citeshttps://doi.org/10.2172/6783967openalex-snapshot
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]
inferred← citeshttps://doi.org/10.2172/6928298openalex-snapshot
Evaluation of criticality alarm response at the WEMCO Fernald site
inferred← citeshttps://doi.org/10.2172/6995501openalex-snapshot
Advanced Neutron Source (ANS) Project progress report
inferred← citeshttps://doi.org/10.2172/7243377openalex-snapshot
Activation of cobalt by neutrons from the Hiroshima bomb
inferred← citeshttps://doi.org/10.2172/763225openalex-snapshot
R-Matrix Evaluation of {sup 16}O neutron cross sections up to 6.3 MeV
inferred← citeshttps://doi.org/10.2172/777649openalex-snapshot
Production of Probability Tables for the Unresolved-Resonance Region Using the AMPX Cross-section Processing System
inferred← citeshttps://doi.org/10.2172/777696openalex-snapshot
SWANS: A Prototypic SCALE Criticality Sequence for Automated Optimization Using the SWAN Methodology
inferred← citeshttps://doi.org/10.2172/777704openalex-snapshot
Criticality Calculations of Fresh LEU and MOX Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant
inferred← citeshttps://doi.org/10.2172/778852openalex-snapshot
INITIAL SUMMARY REPORT FOR REPOSITORY/WASTE PACKAGE ADVANCED CONCEPTUAL DESIGN
inferred← citeshttps://doi.org/10.2172/786752openalex-snapshot
Coupling of MASH-MORSE Adjoint Leakages with Space- and Time-Dependent Plume Radiation Sources
inferred← citeshttps://doi.org/10.2172/787472openalex-snapshot
Cross Sections and Source Spectrum for Nagasaki Dose Reconstruction for Risk Estimation
inferred← citeshttps://doi.org/10.2172/788661openalex-snapshot
Fiscal Year 2001 Status Report for the Investigation of Reactivity Effects Due to Perturbations in Cross-Section Temperature
inferred← citeshttps://doi.org/10.2172/797486openalex-snapshot
Verification and validation of XSDRNPM code for tank waste calculations
inferred← citeshttps://doi.org/10.2172/814059openalex-snapshot
Computational Benchmark for Estimation of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
inferred← citeshttps://doi.org/10.2172/814092openalex-snapshot
Validation and Comparison of KENO V.a and KENO-VI
inferred← citeshttps://doi.org/10.2172/814104openalex-snapshot
Characteristics of Spent Fuel from Plutonium Disposition Reactors, Vol. 1: The Combustion Engineering System 80+ Pressurized-Water-Reactor Design
inferred← citeshttps://doi.org/10.2172/814107openalex-snapshot
An Extension of the Validation of SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel
inferred← citeshttps://doi.org/10.2172/814140openalex-snapshot
KENO V.a Primer: A Primer for Criticality Calculations with SCALE/KENO V.a Using CSPAN for Input
inferred← citeshttps://doi.org/10.2172/814165openalex-snapshot
Plutonium Production Using Natural Uranium From the Front-End of the Nuclear Fuel Cycle
inferred← citeshttps://doi.org/10.2172/814219openalex-snapshot
Parametric Study of the Effect of Burnable Poison Rods for PWR Burnup Credit
inferred← citeshttps://doi.org/10.2172/814237openalex-snapshot
Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages
inferred← citeshttps://doi.org/10.2172/814254openalex-snapshot
Criticality Safety Review of 2 1/2-, 10-, and 14-Ton UF(Sub 6) Cylinders
inferred← citeshttps://doi.org/10.2172/814258openalex-snapshot
Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel
inferred← citeshttps://doi.org/10.2172/814373openalex-snapshot
Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 1-Summary
inferred← citeshttps://doi.org/10.2172/814433openalex-snapshot
Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
inferred← citeshttps://doi.org/10.2172/814444openalex-snapshot
Investigation of Burnup Credit Modeling Issues Associated with BWR Fuel
inferred← citeshttps://doi.org/10.2172/814464openalex-snapshot
Design Parameters for a Natural Uranium UO{sub 3} or U{sub 3}O{sub 8} Fueled Nuclear Reactor
inferred← citeshttps://doi.org/10.2172/814524openalex-snapshot
OPUS/PlotOPUS: An ORIGEN-S Post-Processing Utility and Plotting Program for SCALE
inferred← citeshttps://doi.org/10.2172/814530openalex-snapshot
Recommendations on Fuel Parameters for Standard Technical Specifications for Spent Fuel Storage Casks
inferred← citeshttps://doi.org/10.2172/814537openalex-snapshot
DOE NCSP Review of TRUPACT-II/HalfPACT Fissile Limits
inferred← citeshttps://doi.org/10.2172/814589openalex-snapshot
Analysis of Fresh Fuel Critical Experiments Appropriate for Burnup Credit Validation
inferred← citeshttps://doi.org/10.2172/814592openalex-snapshot
Assessment of the Available (Sup 233)U Cross Sections Evaluations in the Calculation of Critical Benchmark Experiments
inferred← citeshttps://doi.org/10.2172/822601openalex-snapshot
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
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