Critical experiments with concrete-reflected Fast Test Reactor fuel pins in water
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5083569
Criticality benchmark-type data are obtained on four undermoderated FTR (Fast Test Reactor) fuel pin-water lattices with concrete reflection. The experiments were designed to serve as benchmarks for validating computer codes and nuclear data used in calculations of mixed plutonium and uranium systems. These particular experiments provide measurement data on concrete reflectors that can be used for checking not only ''concrete cross sections''but also the computer modeling of systems involving concrete reflectors. 1 ref.
- Research Organization:
- Battelle, Pac Northwest Lab, Richland, Wash
- OSTI ID:
- 5083569
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 49:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Critical Experiments with Fast Test Reactor Fuel Pins in Water
Summary of experimental data for critical arrays of water moderated Fast Test Reactor fuel
Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator
Conference
·
Sat Nov 11 23:00:00 EST 1978
· Transactions of the American Nuclear Society
·
OSTI ID:6526274
Summary of experimental data for critical arrays of water moderated Fast Test Reactor fuel
Technical Report
·
Thu Apr 30 20:00:00 EDT 1981
·
OSTI ID:6463812
Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator
Technical Report
·
Sun Nov 30 19:00:00 EST 1986
·
OSTI ID:10132997
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BENCHMARKS
CRITICALITY
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
NEUTRON REFLECTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BENCHMARKS
CRITICALITY
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
NEUTRON REFLECTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS