Specifications for the JASPER Program attenuation experiment
An integral shielding experiment has been designed to investigate neutron penetration through benchmark and representative mockups of the radial shield designs for advanced sodium-cooled reactor concepts. The experiment will be performed in FY 1986 at the ORNL Tower Shielding Facility to study neutron penetration through various combinations of graphite, boron carbide, and steel configurations using representative near-core and sodium-pool source spectra. Detailed configuration descriptions and measurement specifications for the experiment are included.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 436291
- Report Number(s):
- ORNL/LMR/AC-86/5; ON: DE97003538
- Resource Relation:
- Other Information: PBD: [1986]
- Country of Publication:
- United States
- Language:
- English
Similar Records
Measurements for the JASPER Program radial shield attenuation experiment
Measurements for the Jasper Program intermediate heat exchanger experiment
Measurements for the JASPER program Axial Shield Experiment
Technical Report
·
Fri May 01 00:00:00 EDT 1987
·
OSTI ID:436291
Measurements for the Jasper Program intermediate heat exchanger experiment
Technical Report
·
Wed Jul 01 00:00:00 EDT 1992
·
OSTI ID:436291
+2 more
Measurements for the JASPER program Axial Shield Experiment
Technical Report
·
Thu Aug 01 00:00:00 EDT 1991
·
OSTI ID:436291
+2 more
Related Subjects
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
22 NUCLEAR REACTOR TECHNOLOGY
LMFBR TYPE REACTORS
SHIELDING
COORDINATED RESEARCH PROGRAMS
SHIELDS
ATTENUATION
EXPERIMENT PLANNING
SPECIFICATIONS
NEUTRON TRANSPORT
DESIGN
TSR-1 REACTOR
TSR-2 REACTOR
USA
JAPAN
INTERNATIONAL COOPERATION
REACTOR MATERIALS
STAINLESS STEEL-304
GRAPHITE
BORON CARBIDES
ALUMINIUM
REACTOR PHYSICS
22 NUCLEAR REACTOR TECHNOLOGY
LMFBR TYPE REACTORS
SHIELDING
COORDINATED RESEARCH PROGRAMS
SHIELDS
ATTENUATION
EXPERIMENT PLANNING
SPECIFICATIONS
NEUTRON TRANSPORT
DESIGN
TSR-1 REACTOR
TSR-2 REACTOR
USA
JAPAN
INTERNATIONAL COOPERATION
REACTOR MATERIALS
STAINLESS STEEL-304
GRAPHITE
BORON CARBIDES
ALUMINIUM
REACTOR PHYSICS