Organic-Cooled, Heavy Water-Moderated, U-233 Fueled Lattice Experiments
- Brookhaven National Laboratory (BNL), Upton, NY (United States)
Measurements of material buckling and thermal neutron flux distributions were made in exponential lattices containing the "kilo-rod" fuel pins. The purpose of these measurements was to provide a few definitive data points which can be used to verify design calculations for large power reactors utilizing uranium-233 and thorium fuel with organic coolant and heavy water moderator. consequently, a few lattices were chosen which were consistent with the conceptual design of such a reactor, after consultation with representatives of the Babcock & Wilcox Co. The "kilo-rod" fuel pins are not particularly well suited for these experiments because of their high U-233 content and short active fuel length. Consequently, stainless steel canisters were incorporated in the design to reduce the material buckling and to allow full utilization of the 800 "kilo-rod" fuel pins which were available. In addition, it was decided to make the measurements in a bare assembly, i.e. unreflected assembly, in order to minimize the effects of neutron spectral transients which may be generated at the core-reflector interface. Comparisons are made between the experimental data and calculations using the Methuselah reactor code. No attempt has been made to compare this reactor code with others, since it was chosen as the only appropriate code which was immediately available at BNL. Moreover, it proved to be convenient in planning the experimental program and interpreting the data as it was generated.
- Research Organization:
- Brookhaven National Laboratory (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(30-2)-GEN-16
- NSA Number:
- NSA-21-019457
- OSTI ID:
- 4452280
- Report Number(s):
- BNL-50012
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-67
- Country of Publication:
- United States
- Language:
- English
Similar Records
Critical and Subcritical Californium Source Driven Noise Analysis Experiments with Fresh PWR Fuels Pins
High conversion Th-U{sup 233} fuel assembly for current generation of PWRs
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BUCKLING
COMPUTERS
EXPONENTIAL PILES
FUEL ELEMENTS
FUELS
HEAVY WATER MODERATOR
MEASUREMENT
METHUSELAH-CODE
NEUTRONS
ORGANIC COOLANT
PROGRAMMING
REACTORS
THORIUM OXIDES
URANIUM 233
Nuclear Criticality Safety Program (NCSP)
Criticality
Fuel Elements
Computers
Buckling
U-233
Uranium 233
Thorium
Fuel
N38550* -Research & Test Reactors & Critical Assemblies- Fuels