This report discusses work that has been done to upgrade the ORIGEN2 code cross sections to be compatible with the WIMS computer code data. Because of the changes in the ORIGEN2 calculations. Details on changes made to the ORIGEN2 computer code and the Radnuc code will be discussed along with additional work that should be done in the future to upgrade both ORIGEN2 and Radnuc. A detailed historical description of how source terms have been generated for N Reactor fuel stored in the K Basins has been generated. The neutron source discussed in this description was generated by the WIMS computer code (Gubbins et al. 1982) because of known shortcomings in the ORIGEN2 (Croff 1980) cross sections. Another document includes a discussion of the ORI...
Cross-section libraries for the ORIGEN-ARP system were extended to include four non-U.S. reactor typ...
ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiograp...
Calculation of neutron activation of proposed fusion reactors requires a library of neutron-activati...
This text is intended to be a brief outline of the ORIGEN2 computer code, which is a revised and upd...
This text is intended to be a brief outline of the ORIGEN2 computer code which is a revised and upda...
ORIGEN2 is a versatile point depletion and decay computer code for use in simulating nuclear fuel cy...
Vol. 2, Rev. 6F7.iii ORIGEN-S computes time-dependent concentrations and source terms of a large num...
The ORIGEN-Z-1-11 in its basic calculating method is derived from the ORNL point depletion code ORIG...
The standard cross-section library for light-water reactor (LWR) analyses used by the ORIGEN-S deple...
The submitted manuscript has been authored by a contractor of the U.S. Government under contract No....
This report describes how to use a revised version of the ORIGEN computer code, designated ORIGEN2. ...
The Oak Ridge National Laboratory computer code, ORIGEN2.2 (CCC-371, 2002), was used to obtain the e...
This report describes how to use the FORIG computer code to solve isotope-generation and depletion p...
Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2...
Abstract. ORIGEN is a widely used computer code for calculating the buildup, decay, and processing o...
Cross-section libraries for the ORIGEN-ARP system were extended to include four non-U.S. reactor typ...
ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiograp...
Calculation of neutron activation of proposed fusion reactors requires a library of neutron-activati...
This text is intended to be a brief outline of the ORIGEN2 computer code, which is a revised and upd...
This text is intended to be a brief outline of the ORIGEN2 computer code which is a revised and upda...
ORIGEN2 is a versatile point depletion and decay computer code for use in simulating nuclear fuel cy...
Vol. 2, Rev. 6F7.iii ORIGEN-S computes time-dependent concentrations and source terms of a large num...
The ORIGEN-Z-1-11 in its basic calculating method is derived from the ORNL point depletion code ORIG...
The standard cross-section library for light-water reactor (LWR) analyses used by the ORIGEN-S deple...
The submitted manuscript has been authored by a contractor of the U.S. Government under contract No....
This report describes how to use a revised version of the ORIGEN computer code, designated ORIGEN2. ...
The Oak Ridge National Laboratory computer code, ORIGEN2.2 (CCC-371, 2002), was used to obtain the e...
This report describes how to use the FORIG computer code to solve isotope-generation and depletion p...
Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2...
Abstract. ORIGEN is a widely used computer code for calculating the buildup, decay, and processing o...
Cross-section libraries for the ORIGEN-ARP system were extended to include four non-U.S. reactor typ...
ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiograp...
Calculation of neutron activation of proposed fusion reactors requires a library of neutron-activati...