GRESS translation of the ORIGEN2 code

Technical Report · Thu May 01 04:00:00 EDT 1986

DOI:https://doi.org/10.2172/5752946· OSTI ID:5752946

Pin, F. G.; Wright, R. Q.

ORIGEN2 is a widely used point-depletion and radioactive-decay computer code for use in simulating nuclear fuel cycles and/or spent fuel characteristics. In typical applications the code calculates chain buildup and decay of more than 1600 radionuclides and elements. This report describes the addition to the ORIGEN2 code of an automated sensitivity calculation capability by means of the GRESS precompiler. The GRESS precompiler uses computer calculus to automatically enhance FORTRAN computer codes with derivative-taking capabilities. From these derivatives generated concurrently with the normal results, sensitivities of any variable used in the code with respect to any other variable or input parameter can readily be obtained. The added sensitivity calculation capability is verified on a sample problem involving fuel burnup under specified power, radioactive decay, and material irradiation under specified flux. The accuracy of the GRESS results is demonstrated using comparisons with the results of perturbation analyses.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5752946
• Report Number(s): ORNL/TM-9694; ON: DE86011355
• Country of Publication: United States
• Language: English

Related Subjects

052000* -- Nuclear Fuels-- Waste Management
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
COMPUTER CODES
COMPUTERIZED SIMULATION
DECAY
ENERGY SOURCES
FUEL CYCLE
FUELS
ISOTOPES
MATERIALS
MODIFICATIONS
NUCLEAR FUELS
O CODES
RADIOISOTOPES
REACTOR MATERIALS
SENSITIVITY ANALYSIS
SIMULATION
SPENT FUELS