Version of ORIGEN2 with automated sensitivity-calculation capability
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6660551
The ORIGEN2 code is a widely used point-depletion and radioactive-decay computer code for use in simulating nuclear fuel cycles and/or spent fuel characteristics. The code calculates the amount of each nuclide being considered in the problem at a specified number of times, and on request, a data base of conversion factors relating mass compositions to specific material characteristics is used to calculate and print the total nuclide-dependent radioactivity, thermal power, and toxicity, as well as absorption, fission, neutron emission, and photon emission rates. The purpose of this paper is to report on the availability of a version of ORIGEN2 that will calculate, on option, the derivative of all responses with respect to any variable used in the code.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 6660551
- Report Number(s):
- CONF-860610-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
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