Summary of Experimental and Calculational Results from the Joint USDOE/PNC Criticality Data Development Program
Conference
·
OSTI ID:5533508
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Engineering Technology Division
- 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
Similar Records
Validation Studies Using Joint USDOE/PNC Critical Experiments
Summary of Critical Experimental Data from the Joint USDOE/PNC Criticality Data Development Program
Criticality data and validation studies of arrays of mixed-oxide fuel pins in aqueous and organic solutions
Conference
·
Mon Oct 19 00:00:00 EDT 1987
·
OSTI ID:7026755
Summary of Critical Experimental Data from the Joint USDOE/PNC Criticality Data Development Program
Conference
·
Mon Sep 09 00:00:00 EDT 1991
·
OSTI ID:5654817
Criticality data and validation studies of arrays of mixed-oxide fuel pins in aqueous and organic solutions
Journal Article
·
Thu Sep 01 00:00:00 EDT 1994
· Nuclear Technology; (United States)
·
OSTI ID:6903596
Related Subjects
050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
052002 -- Nuclear Fuels-- Waste Disposal & Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
97 MATHEMATICS AND COMPUTING
COMPUTER CALCULATIONS
COMPUTER CODES
CONSOLIDATED FUEL REPROCESSING PROGRAM
COOPERATION
COORDINATED RESEARCH PROGRAMS
CRITICALITY
CROSS SECTIONS
DATA
DISSOLUTION
Dancoff Factor
ENERGY SOURCES
EXPERIMENTAL DATA
EXTRACTION
FISSILE MATERIALS
FISSIONABLE MATERIALS
FUEL CYCLE
FUEL REPROCESSING PLANTS
FUELS
Fissile Solution Storage
Fuel Dissolution
Fuel Pin Arrays
INFORMATION
INTERNATIONAL COOPERATION
JAPANESE ORGANIZATIONS
MANAGEMENT
MATERIALS
Mixed Oxide (MOX)
Monte Carlo
NATIONAL ORGANIZATIONS
NEUTRON SPECTRA
NITAWL Code
NUCLEAR FACILITIES
NUCLEAR FUELS
NUMERICAL DATA
Nordheim Integral Method
Nuclear Criticality Safety Program (NCSP)
Nuclear Fuel Dissolver
PNC
RADIOACTIVE WASTE STORAGE
REACTOR MATERIALS
RESEARCH PROGRAMS
S CODES
SCALE Code
SEPARATION PROCESSES
SOLVENT EXTRACTION
SPECTRA
STORAGE
US DOE
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE STORAGE
Waste Storage
052002 -- Nuclear Fuels-- Waste Disposal & Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
97 MATHEMATICS AND COMPUTING
COMPUTER CALCULATIONS
COMPUTER CODES
CONSOLIDATED FUEL REPROCESSING PROGRAM
COOPERATION
COORDINATED RESEARCH PROGRAMS
CRITICALITY
CROSS SECTIONS
DATA
DISSOLUTION
Dancoff Factor
ENERGY SOURCES
EXPERIMENTAL DATA
EXTRACTION
FISSILE MATERIALS
FISSIONABLE MATERIALS
FUEL CYCLE
FUEL REPROCESSING PLANTS
FUELS
Fissile Solution Storage
Fuel Dissolution
Fuel Pin Arrays
INFORMATION
INTERNATIONAL COOPERATION
JAPANESE ORGANIZATIONS
MANAGEMENT
MATERIALS
Mixed Oxide (MOX)
Monte Carlo
NATIONAL ORGANIZATIONS
NEUTRON SPECTRA
NITAWL Code
NUCLEAR FACILITIES
NUCLEAR FUELS
NUMERICAL DATA
Nordheim Integral Method
Nuclear Criticality Safety Program (NCSP)
Nuclear Fuel Dissolver
PNC
RADIOACTIVE WASTE STORAGE
REACTOR MATERIALS
RESEARCH PROGRAMS
S CODES
SCALE Code
SEPARATION PROCESSES
SOLVENT EXTRACTION
SPECTRA
STORAGE
US DOE
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE STORAGE
Waste Storage