Since its inception in 1962, RSICC has evolved into one of the world’s leading resources for a broad range of the best available nuclear computational tools and services. RSICC software and data collections provide in-depth coverage of radiation transport and safety topics encompassing, but not limited to:

Physics of the interaction of radiation with matter
Radiation production and sources
Criticality safety
Radiation protection and shielding
Radiation detectors and measurements
Shielding materials properties
Shields and shipping cask design
Radiation waste management
Radiological safety and assessment
Atmospheric dispersion and environmental dose
Radiation dose in medical applications
Space shielding applications

SCALE 6.2 Release

RSICC is pleased to announce the release of SCALE 6.2 from Oak Ridge National Laboratory. The SCALE code system, which is a widely used modeling and simulation suite for nuclear safety analysis and design that is developed, maintained, tested, and managed by the Reactor and Nuclear Systems Division (RNSD) of the Oak Ridge National Laboratory (ORNL). SCALE provides a comprehensive, verified and validated, user-friendly tool set for criticality safety, reactor physics, radiation shielding, radioactive source term characterization, and sensitivity and uncertainty analysis. Since 1980, regulators, licensees, and research institutions around the world have used SCALE for safety analysis and design. SCALE provides an integrated framework with dozens of computational modules, including three deterministic and three Monte Carlo radiation transport solvers selected based on the user’s desired solution strategy.

In addition, SCALE 6.2 also includes a new production release of AMPX-6. AMPX is used to process Evaluated Nuclear Data File (ENDF) nuclear data evaluations, as well as other data sources that use the ENDF format, to provide nuclear data libraries for use in modern transport code packages. AMPX is primarily used to provide nuclear data libraries for the SCALE code package, but AMPX can be used to produce data libraries that can be used by other transport codes. AMPX provides continuous energy (CE) and multi-group (MG) neutron and gamma cross-section data. Also, AMPX provides cross-section uncertainty or covariance data for use with sensitivity/uncertainty analysis tools. Furthermore, AMPX can be used to process ENDF/B evaluations to produce depletion and decay libraries needed by depletion codes such as ORIGEN.

SCALE 6.2 provides many new capabilities and significant improvements of existing features. Please see the SCALE 6.2 abstract for more information.

RSICC Deploys Secure Cloud Server

RSICC would like to inform our customers that we are deploying a secure cloud computing system that will be made available to our customers that meet following criteria:

1. The individual is from a country for which a specific export authorization would be required;
2. The individual would likely be denied or have restricted access to software; and
3. It is in the interest of the U.S. government to provide access to the software.

Individuals that meet the criteria listed above and are in one of the following categories will automatically be considered for access:

1. Individuals that indicate that they are collaborating with US organizations such as US national laboratories or US universities;
2. Individuals that indicate that they are teaching or conducting research at US universities; and
3. Students at US universities.

Other individuals may be granted access to the secure cloud as requested by RSICC’s sponsors and approved by RSICC’s regulators.

RSICC will screen all requests for MCNP6.1, SCALE6.1 and RELAP5/MOD3.3 to determine if an individual qualifies for access to RSICC’s secure cloud computing system. The request will be submitted to our regulators. If approved, the customer will be required to provide specific information to RSICC and agree to certain terms and conditions before being granted access to the system. Individuals that are approved will not be permitted to utilize these codes except on RSICC's secure cloud computing system. If an individual is approved for access to RSICC's secure cloud computing system and does not consent to the terms and conditions, the individual's request will be mark as denied.

The deployment of this system will allow RSICC to grant use of certain codes to some of our customers who otherwise would not be authorized. RSICC would like to thank its sponsors, the Department of Energy's Office of Nuclear Energy and the National Nuclear Security Administration's Office of Nonproliferation and Arms Control, for supporting the development and deployment of this system.

Safety Analysis Report for Packaging (SARP)
Shielding/Criticality Safety Generalist and Analyst Courses
Developed and Conducted by Oak Ridge National Laboratory

Radioactive Material Package Shielding Evaluation and Nuclear Criticality Safety Evaluation Training:

The U.S. Department of Energy (DOE) Packaging Certification Program (PCP), Office of Packaging and Transportation, is offering Safety Analysis Report for Packaging (SARP) shielding and nuclear criticality safety (NCS) courses for SARP generalists and analysts.

June 6-10, 2016
The SARP Generalist Course is designed for project managers, supervisors, NCS/shielding subject matter experts (SME), or SMEs in non-NCS/shielding technical areas (e.g., structural, thermal, package design, etc.) who need to better understand how the NCS/shielding analyses fit in the broader SARP documentation. Specifically, the Generalist Course provides an overview of the regulations and guidelines for the criticality and shielding analysis for a SARP, and the course shows how the NCS/shielding chapters integrate with the other parts of the SARP. Students in the Generalist Course will review an actual SARP document after the course material is presented to emphasize the key elements of the shielding and criticality analyses.

Sept. 12-16, 2016
The Analysts Course will provide detailed training on the radioactive material package shielding analyses and NCS evaluation fundamentals needed by analysts/practitioners (i.e., safety analysts and/or technical reviewers) to prepare and/or review technical analyses for the SARP documentation. The Analyst Course also provides an overview of regulations and guidelines in addition to detailed in-class exercises associated with the package shielding and NCS analyses. With regard to the in-class exercises, analysis teams will be faced with “staged” SARP examples in which a number of important decision processes in the generation of a SARP will be demonstrated and discussed.

Both the SARP Generalist and SARP Analyst Courses will be offered in Fiscal Year 2016.

The SARP Generalist Course will be held at Oak Ridge National Laboratory in Oak Ridge, TN. The SARP Generalist Course is scheduled for June 6-10, 2016.

The SARP Analyst Course is scheduled for Sept. 12-16, 2016 also at Oak Ridge National Laboratory in Oak Ridge, TN.

Further information will be posted as soon as it is available.

Contact Douglas G. Bowen by email or phone (865) 576-0315.

The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.