Neutron Reaction Rate Measurements in an Organically Moderated Lattice of FTR Fuel Pins
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5579054
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
Critical experiments are being conducted in the Battelle Pacific Northwest Lab.'s Critical Mass Lab. for the Consolidated Fuel Reprocessing Program using a variety of fast test reactor (FTR) fuel pin configurations and fissile solution concentrations. These experiments are being performed as part of a joint agreement between the US Dept. of Energy and the Power Reactor and Nuclear Fuel Development Corp. of Japan on criticality data development. On selected experimental assemblies in this program, absolute neutron reaction rates are being measured to provide basic neutron physics data for use in evaluating nuclear cross sections and calculational methods. The results obtained from the initial set of measurements in this program are presented in this paper. The initial series of reaction rate measurements were made in an experimental critical assembly of FTR fuel pins immersed in a tributylphosphate-normal paraffin hydrocarbon mixture.
- Research Organization:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5579054
- 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
Analytical Study of Criticality Experiments of Organic and Light-Water-Moderated Mixed-Oxide Fuel Pin Arrays
Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator
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:5579046
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
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
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
CRITICALITY
EPITHERMAL REACTORS
Experimental Critical Assembly
FAST REACTORS
FUEL ELEMENTS
FUEL PINS
Fast Test Reactor (FTR)
Fuel Pins
JAPANESE ORGANIZATIONS
KINETICS
MODERATORS
NATIONAL ORGANIZATIONS
Nuclear Criticality Safety Program (NCSP)
ORGANIC COMPOUNDS
PNC
REACTOR COMPONENTS
REACTOR KINETICS
REACTOR LATTICES
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TEST REACTORS
US DOE
US ERDA
US ORGANIZATIONS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
BATTELLE PACIFIC NORTHWEST LABORATORIES
CRITICALITY
EPITHERMAL REACTORS
Experimental Critical Assembly
FAST REACTORS
FUEL ELEMENTS
FUEL PINS
Fast Test Reactor (FTR)
Fuel Pins
JAPANESE ORGANIZATIONS
KINETICS
MODERATORS
NATIONAL ORGANIZATIONS
Nuclear Criticality Safety Program (NCSP)
ORGANIC COMPOUNDS
PNC
REACTOR COMPONENTS
REACTOR KINETICS
REACTOR LATTICES
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TEST REACTORS
US DOE
US ERDA
US ORGANIZATIONS