Validation Studies Performed with Mixed Pu + U Aqueous Critical Experiments in Annular Geometry
Conference
·
OSTI ID:5168266
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
This paper discusses the results of a calculational study that was performed to validate the SCALE computer code system using data from critical experiments performed with mixed Pu /plus/ U aqueous solutions. The critical experiments were conducted in an annular vessel where the fissile solution was placed in the annulus, and various inserts and bottles containing fissile solution were located in the inner portion of the vessel.
- Research Organization:
- Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5168266
- Report Number(s):
- CONF-880601-13-Summ.; ON: DE88005291
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Conference
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Thu Dec 31 23:00:00 EST 1987
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:5626433
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· Nuclear Technology; (United States)
·
OSTI ID:6996416
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·
OSTI ID:1070035
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DATA BASE MANAGEMENT
DISPERSIONS
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METALS
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