Reactor Physics Quarterly Report (April, May, June 1969)

Technical Report · Fri Aug 01 04:00:00 EDT 1969

DOI:https://doi.org/10.2172/4764440· OSTI ID:4764440

Schmid, L. C. ^[1]; Clayton, E. D. ^[1]; Heineman, R. E. ^[1]

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

Updates are provided for the following topics: (1) Reactor Theory and Code Development, use of Fixed Point Arithmetic in Monte Carlo Codes, Etox - A Code to Calculate Group Constants for Nuclear Reactor Calculations, Time-Variant Isotopic Transmutation, Theoretical Calculations of Optical-Model Potentials for Use in Nuclear Reaction Studies on Light Nuclei, Hard Core Effects with a Single, Separable T Matric, Equivalence of the ∂' and the Hard Core Potentials, Battelle Revised Flare (BFR-1), The Intermediate Resonance Approximation, Analytical Correlations of Measured Power Distributions, Measurement of the Temperature Coefficient of Reactivity Using the Endogenous Pulsed Source Method, The Shape of Peaks in Gamma-Ray Spectra from Ge(Li) Detectors; (2) Thermal Reactors, Theoretical Correlation of the PRTR Batch Core Experiment; (3) Fast Reactors, Nuclear and Process Technology; (4) Critical Mass Physics, Criticality of Poisoned PuO₂ Fueled Assemblies, Criticality of Undermoderated Plutonium, Criticality of Mixed PuO₂-UO₂ Systems, Surface Multiplication, Impact of Criticality Safety on the Fabrication of LMFBR Fuel.

• 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-23-047233
• OSTI ID: 4764440
• Report Number(s): BNWL-1150
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BURNUP
COMPUTERS
COOLANT LOOPS
CRITICALITY
Code Development
Criticality
DIGITAL SYSTEMS
Dynamics
EFFICIENCY
ERRORS
FAST REACTORS
FLUID FLOW
FTR
FUEL CYCLE
FUELS
Fabrication
Fixed Point Arithmetic
Kinetics
Monte Carlo Code
N38510* --Research & Test Reactors & Critical Assemblies-- Kinetics & Dynamics
Nuclear Criticality Safety Program (NCSP)
OPTIMIZATION
PLUTONIUM OXIDES
PROGRAMMING
PRTR
Quarterly Report
REACTIVITY
REACTOR CORE
RESEARCH REACTORS
Reactor Theory
Research
Safety
THERMAL NEUTRONS
URANIUM DIOXIDE