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Summary of Experimental and Calculational Results from the Joint USDOE/PNC Criticality Data Development Program

Conference ·
OSTI ID:5533508
 [1];  [2]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Engineering Technology Division
  2. Power Reactor and Nuclear Fuel Development Corporation (PNC), Tokai, Ibakari (Japan)
A joint exchange program on the subject of criticality data development was completed in August 1988. The program was between the US Department of Energy (DOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The primary purpose of the program was to perform critical experiments to allow validation of computer codes and cross-section libraries used for safety analyses for facilities that recycle nuclear fuel. The experiments spanned the range of neutron spectra from the very under-moderated condition (H/Pu ratio=22) to the very over-moderated condition (H/Pu ratio=2220). Based on computations performed at the Oak Ridge National Laboratory (ORNL), the average calculated k-effective for these experiments is 1.004. Calculated k-effectives ranged from 0.991 to 1.021, and the standard deviation of these results is 0.006. PNC staff have obtained similar calculational results in their validation studies. The good agreement between experiment and calculation gives confidence that the calculational methods can be applied to similar plant conditions.
Research Organization:
Power Reactor and Nuclear Fuel Development Corporation (PNC), Tokai, Ibakari (Japan); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Engineering Technology Division
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Facilities, Fuel Cycle, and Test Programs
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5533508
Report Number(s):
CONF-891103-26; ON: DE89016290
Country of Publication:
United States
Language:
English

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