Analytical Study of Criticality Experiments of Organic and Light-Water-Moderated Mixed-Oxide Fuel Pin Arrays
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5579046
- PNC, Oarai (Japan)
As part of a joint criticality data development program between the Power Reactor and Nuclear Fuel Development Corp. of Japan and the US Dept. of Energy, critical experiments have been conducted with organically moderated fast test reactor (FTR) mixed-oxide fuel pin arrays. The neutronic characteristics of an organic moderator can be examined by comparing the results of these experiments with the results of the same type of experiments performed with light-water-moderated systems. In recent experiments performed at the Battelle Pacific Northwest Laboratory's Critical Mass Laboratory, five distances of the lattice pitches were utilized that span from soft to hard neutron energy spectra. These lattice pitches range from a volume ratio of 1.62 to 18.13. The organic solution consisted of approx. 32 vol % tributyl phosphate (TBP) and 68 vol % normal paraffin hydrocarbon (NPH). Results obtained by benchmark analyses of these experiments are discussed in this paper.
- Research Organization:
- PNC, Oarai (Japan)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5579046
- Report Number(s):
- CONF-870601-
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 54
- Country of Publication:
- United States
- Language:
- English
Similar Records
Neutron Reaction Rate Measurements in an Organically Moderated Lattice of FTR Fuel Pins
Calculational Assessment of Critical Experiments with Mixed-Oxide Fuel Pin Arrays Moderated by Organic Solution
Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator
Conference
·
Sun Jun 07 00:00:00 EDT 1987
· Transactions of the American Nuclear Society
·
OSTI ID:5579054
Calculational Assessment of Critical Experiments with Mixed-Oxide Fuel Pin Arrays Moderated by Organic Solution
Conference
·
Sun Jun 07 00:00:00 EDT 1987
· Transactions of the American Nuclear Society
·
OSTI ID:5460479
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
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
BATTELLE PACIFIC NORTHWEST LABORATORIES
BENCHMARKS
BUTYL PHOSPHATES
Benchmark Analyses
CRITICALITY
EPITHERMAL REACTORS
ESTERS
FAST REACTORS
FUEL ASSEMBLIES
FUELS
Fast Test Reactor (FTR)
HYDROGEN COMPOUNDS
JAPANESE ORGANIZATIONS
MIXED OXIDE FUELS
MODERATORS
MULTIPLICATION FACTORS
NATIONAL ORGANIZATIONS
Nuclear Criticality Safety Program (NCSP)
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
OXYGEN COMPOUNDS
PHOSPHORIC ACID ESTERS
PNC
REACTOR LATTICES
REACTORS
RESEARCH AND TEST REACTORS
Results
SOLID FUELS
TBP
TEST REACTORS
US DOE
US ERDA
US ORGANIZATIONS
WATER
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
BATTELLE PACIFIC NORTHWEST LABORATORIES
BENCHMARKS
BUTYL PHOSPHATES
Benchmark Analyses
CRITICALITY
EPITHERMAL REACTORS
ESTERS
FAST REACTORS
FUEL ASSEMBLIES
FUELS
Fast Test Reactor (FTR)
HYDROGEN COMPOUNDS
JAPANESE ORGANIZATIONS
MIXED OXIDE FUELS
MODERATORS
MULTIPLICATION FACTORS
NATIONAL ORGANIZATIONS
Nuclear Criticality Safety Program (NCSP)
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
OXYGEN COMPOUNDS
PHOSPHORIC ACID ESTERS
PNC
REACTOR LATTICES
REACTORS
RESEARCH AND TEST REACTORS
Results
SOLID FUELS
TBP
TEST REACTORS
US DOE
US ERDA
US ORGANIZATIONS
WATER