Technical Activities Quarterly Report: AEC Reactor Development and Technology Programs (July, August, September 1970)

Technical Report · Thu Oct 01 04:00:00 EDT 1970

DOI:https://doi.org/10.2172/4048924· OSTI ID:4048924

Dawson, F. G. ^[1]

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

Updates include: (1) Plutonium Utilization Program, including PRTR Fuel Evaluations, Transient Testing, Plutonium and Fission Product Migration in Mixed-Oxide Fuels During Irradiation, High Exposure Plutonium Studies, Defect Testing, Saxton Fuel Examination, Monte Carlo Thermal Neutron Sampling Model for Water, The Determination of Ratios of Effective Cross Sections from Burnup Data from the Saxton Plutonium Program, PuO₂ Particle Size Reactivity Effect, GRANIT: A Code for Calculating Position Dependent Thermal Neutron Spectra in Double Heterogenous Systems by the Integral Transport Method; (2) High Temperature Reactor Physics Program, including Measurement of k_∞ for a ThO₂-²³⁵U₂ HTGR Lattice as a Function of Temperature, Measurement of k_∞(T) for a ThO₂-²³³U₂ HTGR Lattice in HTLTR, ThO₂-PuO₂ HTGR Experiment in HTLTR, Reactivity Measurements and the In-Hour Equation, Evaluating Potential Deformation in the Vertical Safety Rods at the High Temperature Lattice Test Reactor, Determining Feasibility of Using the Fast Neutron Cavity in the PCTR for Cross-Section Evaluation; (3) Phoenix Studies; (4) Steady State and Transient Subchannel Code Development and Data Analysis, including COBRA-II Computer Program, Experimental study of Flow Structure in Rod Bundles; (5) Plutonium Criticality Studies, including Critical Experiments with Unmoderated PuO₂; (6) Calculations of Potential Environmental Radiological Consequences of Reactor Accidents; (7) Nuclear Graphite, including In-Reactor Creep, Radiolytic Reactions in Graphite Moderated Reactors, Effect of sample Size on Dimensional Stability, High-Temperature Irradiations, Analysis of Coolant-Graphite Reactions, Mechanism of Irradiation Damage; (8) Corrosion Product Transport Study, including Crud Generator Studies, Iron Analysis Procedure, and System Design (9) Air Pressurized Water Loop Operation and Maintenance.

• 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-25-018098
• OSTI ID: 4048924
• Report Number(s): BNWL-1522-1
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
54 ENVIRONMENTAL SCIENCES
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
Accidents
Analysis
BURNUP
CHEMICAL REACTIONS
CONTROL ELEMENTS
CORROSION
CRITICAL ASSEMBLIES
CRITICALITY
CROSS SECTIONS
Corrosion
Creep
Criticality
DEFORMATION
DIFFUSION
EXCURSIONS
FISSION PRODUCTS
FLUID FLOW
FUEL CANS
FUEL CYCLE
FUEL ELEMENTS
FUELS
GAMMA RADIATION
GRAPHITE
HEAT TRANSFER
HTGR
HTGR TYPE REACTORS
HTLTR
IRRADIATION
ISOTOPE RATIO
LIFETIME
MECHANICAL PROPERTIES
Measurements
N30230 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Properties Evaluations
N30250 --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Radiation Effects
N38100* --Power Reactor Development
N38500 --Research & Test Reactors & Critical Assemblies
NEUTRONS
Nuclear Criticality Safety Program (NCSP)
Nuclear Graphite
PARTICLES
PCTR
PERFORMANCE
PLUTONIUM
PLUTONIUM 240
PLUTONIUM OXIDES
PRODUCTION
PROGRAMMING
PRTR
Phoenix Studies
Plutonium
Quarterly Report
RADIATION DOSES
RADIATION EFFECTS
REACTIVITY
REACTOR KINETICS
REACTOR LATTICES
RODS
Reactivity
Reactor
Safety
TESTING
TRANSIENTS
URANIUM DIOXIDE
Utilization
WATER MODERATED REACTORS
ZIRCALOY
ZONES