Steam-Cooled Fast Breeder Power Reactors Parametric Design Studies

Technical Report · Mon Apr 01 04:00:00 EST 1968

DOI:https://doi.org/10.2172/4519050· OSTI ID:4519050

Fox, J. C. ^[1]; Aase, D. T. ^[1]; Wise, K. R. ^[1]; Altschuler, S. J. ^[1]; Busselman, G. J. ^[1]; Holeman, R. H. ^[1]

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1. Battelle Pacific Northwest Labs., Richland, WA (United States)

The nuclear survey was based on a set of nine combinations of steam inventory and core material volume fractions, designated as cases 0A through 2C. Figure 1 shows the characteristics of these cases and their relationship to the three specific designs evaluated by ORNL. The physics calculation geometric model was based on the Karlsruhe intermediate pressure design. In most calculations, 0.276 in. pins, spherical geometry from 1000 to 10,000 liters, an 18 in. depleted uranium blanket, and a Karlsruhe-type reflector were used. All cases assumed 15% clad-structure of Inconel-625. An equilibrium plutonium isotopic composition of 76.0, 21.0, 2.3, and 0.7% for ²³⁹Pu, ²⁴⁰Pu, ²⁴¹, and ²⁴²Pu, respectively, was used for all cases. The methods used in the physics parametric study were chosen to conform, as closely as possible, to those used by ORNL so that a reasonably valid comparison could be obtained. The ORNL cross section set was used to help eliminate discrepancies in the nuclear analysis. Details of the physics calculations appear under Neutronics Survey.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(45-1)-1830
• NSA Number: NSA-22-027401
• OSTI ID: 4519050
• Report Number(s): BNWL-713
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ANALOG SYSTEMS
ANALYSIS
BREEDING
COMPUTERS
CONFIGURATION
CRITICALITY
Core Material
Criticality
ECONOMICS
EFFICIENCY
ENRICHMENT
FAST NEUTRONS
FUELS
GAS COOLANT
Geometric
Inventory
MOCKUP
Model
N38100* --Power Reactor Development
Nuclear Criticality Safety Program (NCSP)
POWER PLANTS
PRESSURE
REACTIVITY
REACTOR CORE
REACTORS
STEAM
TEMPERATURE
Volume Fractions
WATER COOLANT