SCALE 6.3.1 User Manual

Wieselquist, William; Lefebvre, Robert Alexander

doi:10.2172/1959594

Title: SCALE 6.3.1 User Manual

Full Record
Other Related Research

Abstract

SCALE is a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory under contract with the U.S. Nuclear Regulatory Commission, U.S. Department of Energy, and the National Nuclear Security Administration to perform reactor physics, criticality safety, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs.

Authors:

^[1];

^[1]

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Publication Date:: Wed Feb 01 00:00:00 EST 2023

Research Org.:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA); USNRC

OSTI Identifier:: 1959594

Report Number(s):: ORNL/TM-SCALE-6.3.1
ORNL/TM-SCALE-6.3.1; TRN: US2403171

DOE Contract Number:: AC05-00OR22725

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 97 MATHEMATICS AND COMPUTING; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS

Citation Formats


                    Wieselquist, William, and Lefebvre, Robert Alexander. SCALE 6.3.1 User Manual.  United States: N. p., 2023. 
        Web.  doi:10.2172/1959594.

Copy to clipboard


                    Wieselquist, William, & Lefebvre, Robert Alexander. SCALE 6.3.1 User Manual.  United States.  https://doi.org/10.2172/1959594

Copy to clipboard


                    Wieselquist, William, and Lefebvre, Robert Alexander. 2023.  
        "SCALE 6.3.1 User Manual".  United States.  https://doi.org/10.2172/1959594.  https://www.osti.gov/servlets/purl/1959594.

Copy to clipboard


                    
@article{osti_1959594,

  title        = {SCALE 6.3.1 User Manual},

  author       = {Wieselquist, William and Lefebvre, Robert Alexander},

  abstractNote = {SCALE is a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory under contract with the U.S. Nuclear Regulatory Commission, U.S. Department of Energy, and the National Nuclear Security Administration to perform reactor physics, criticality safety, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs.},

  doi          = {10.2172/1959594},

  url          = {https://www.osti.gov/biblio/1959594},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Wed Feb 01 00:00:00 EST 2023},

  month        = {Wed Feb 01 00:00:00 EST 2023}

}

Copy to clipboard

Technical Report:

View Technical Report

https://doi.org/10.2172/1959594

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

SCALE 6.3.0 User Manual

Technical Report Wieselquist, William; Lefebvre, Robert

SCALE is a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory under contract with the U.S. Nuclear Regulatory Commission, U.S. Department of Energy, and the National Nuclear Security Administration to perform reactor physics, criticality safety, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs.
https://doi.org/10.2172/1909149

Full Text Available
Overview of SCALE system shielding capabilities

Journal Article Broadhead, B; Parks, C - Transactions of the American Nuclear Society

The Nuclear Engineering Applications Section and its sister department, Engineering Applications, at Oak Ridge National Laboratory have had a long-term relationship with the U.S. Nuclear Regulatory Commission (NRC) to provide support in the development and use of the SCALE system analytical tools and cross-section libraries for the criticality, shielding, and thermal review of spent fuel packaging designs and storage pools. Over the years, the use of the SCALE system has grown far beyond the confines of the NRC. The system is used widely in the United States and abroad by government contractors, private industry, and universities to perform (1) problem-dependentmore »« less
SCALE Enhancements for Detailed Cask Dose Rate Analysis - Paper 37

Conference Peplow, Douglas; Radulescu, Georgeta; Williams, Mark; ...

The Nuclear Fuels Storage and Transportation Planning Project and the Used Fuel Disposition Campaign, both under the US Department of Energy (DOE) Office of Nuclear Energy, require the ability to predict k{sub eff}, heat generation and temperature distributions, and external dose rates from any combination of commercial spent nuclear fuel assemblies loaded into any type of licensed cask. Work in the Reactor and Nuclear Systems Division at Oak Ridge National Laboratory has begun to develop the UNF-ST[and]DARDS system (Used Nuclear Fuel Storage, Transportation and Disposal Analysis Resource and Data System) that uses many of the nuclear analysis codes from themore »« less
Photonuclear Physics in SCALE

Technical Report Lefebvre, Robert; Brown, Jesse; Celik, Cihangir; ...

Radiation shielding modeling involves a wide range of applications, such as power reactors, critical experiments, portable sources, linear accelerators, and fusion systems. Particle energy ranges vary from thermal energies to fast energy spectra. MAVRIC, as the radiation shielding sequence of the SCALE code system [1] developed and maintained by Oak Ridge National Laboratory, is capable of modeling both neutron and photon interactions in matter and is widely used by the US Nuclear Regulatory Commission, Department of Energy, the National Nuclear Security Administration, and radiation shielding practitioners all around the world. Although most applications don’t involve highly energetic photons that canmore »« less
https://doi.org/10.2172/2282948

Full Text Available
Analytical Model Methodology Development and Demonstration of Approach on Used Fuel Performance Characterization for Condition of Normal Transportation

Conference Geelhood, Kenneth; Adkins, Harold; Sanborn, Scott; ...

U.S. Nuclear Regulatory Commission (NRC) rules require that used nuclear fuel (UNF) rods maintain their integrity during handling, transportation, and storage to ensure maintenance of the fuel retaining boundary, safety against criticality, and long term fuel retrievability for processing and disposal. Consequently, understanding the mechanical performance of UNF rods under cumulative loading stemming from handling, normal conditions of transport (NCT), and normal conditions of storage (NCS) is necessary as their performance under these conditions establishes part of their safety basis. The U.S. Department of Energy (DOE) commissioned a multi-laboratory team consisting of subject matter experts at Pacific Northwest National Laboratory,more »« less

Similar Records