Download ORIGEN Nuclear Code - Complete Guide & Applications

Download ORIGEN Nuclear Code - Complete Guide & Applications

The ORIGEN code (Oak Ridge Isotope Generation) is a premier computer code developed and maintained by Oak Ridge National Laboratory (ORNL). It is an industry-standard tool for simulating the depletion, decay, and processing of radioactive materials, serving as a critical resource in nuclear engineering and research.

Core Functionalities and Applications

ORIGEN is designed to perform detailed isotope generation and depletion calculations. Its primary applications include:

• Burnup Calculation: The code accurately computes nuclear fuel burnup, a critical parameter measured in megawatt-days per metric ton of heavy metal (MWd/MTU), which indicates how much energy has been extracted from the fuel.

• Activity Estimation: It determines the radioactivity levels of materials irradiated in a neutron flux. This is essential for safety analyses, radiation shielding design, and radioactive waste management strategies.

• Decay Heat Analysis: ORIGEN calculates the heat produced by radioactive decay in spent nuclear fuel, even after the reactor is shut down. This information is vital for designing and assessing cooling systems for fuel pools and storage casks.

• Radiation Source Term Specification: The code can estimate the emission spectra of gamma rays and neutrons from radioactive materials, which is crucial for dosimetry and shielding studies.

Input and Output Structure

Running an ORIGEN simulation requires creating a structured input file that defines the system's parameters. Key input data includes:

• Reactor power level

• Initial fuel mass and composition

• Isotopic concentrations within the fuel

• Irradiation history (power levels over time)

• Reactor type, which loads appropriate cross-section libraries

Upon execution, ORIGEN generates a comprehensive output file containing detailed information used to determine:

• The concentrations of Actinides (e.g., Uranium, Plutonium) and their radioactive decay products (daughters).

• The inventory of Fission Products created from the splitting of heavy nuclei.

• The buildup of Activation Products resulting from neutron irradiation of structural and other materials.

Introduction to Key Command Cards

ORIGEN uses a deck of "cards" to provide instructions. Each card specifies a particular command or parameter set. Understanding these cards is key to controlling the simulation. Some of the most important ones include:

• BUP Card (Burnup): This command instructs the code to calculate the average fuel burnup. It processes the neutron flux and power level data over a specified irradiation period to determine the fuel depletion.

• IRP Card (In-Reactor Processing): This card is used to model the composition of the reactor core inventory during its operational lifetime.

• OPTL Card (Option Library): This card controls the format and type of output tables printed for activation products.

• OPTA Card (Option Actinide): This directive specifies how the output tables for actinides and their decay chains are formatted and presented.

• OPTYE Card (Option Yield): This command allows the user to define the structure and content of the output tables for fission products.

Summary and Download

ORIGEN2 represents the latest and most advanced version of this powerful software suite. It is extensively used in research institutions, regulatory bodies, and universities worldwide for reactor design, fuel cycle analysis, safety assessment, and waste management. By mastering its input card system, users can perform highly complex and customized simulations with extensive detail.

Download the ORIGEN Code:
Access to the ORIGEN code and its associated data libraries is typically managed through the official resources of Oak Ridge National Laboratory. For the most up-to-date version, documentation, and licensing information, please visit the ORNL software distribution page.