Technical Activities Quarterly Report: AEC Reactor Development and Technology Programs (October, November, December 1970; January, February, March 1971)

Technical Report · Tue Jun 01 04:00:00 EDT 1971

DOI:https://doi.org/10.2172/4703785· OSTI ID:4703785

Dawson, F. G. ^[1]

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

Updates includes: (1) Plutonium Utilization Program, including β_eff/$$\ell$$ For a Pu-Enriched H₂O Lattice Containing Water Regions, Experiment-Theory Correlation of PuO₂ Particle Size Reactivity Effect, Measurement of k_∞ and Relative Reaction Rates in an H₂O Moderated UO₂-PuO₂ Particle Size Fueled Lattice, Evaluation of the Relative Strength of PWR Control Clusters for UO₂ and PuO₂/UO₂ Cores, Review of the ENDF/B Description of Deuterim Scattering, Destructive and Nondestructive Analysis of Plutonium Fuels Used in Lattice Experiments, Description of Program Draft, PRTR Fuel Evaluations, Transient Testing; (2) High Temperature Reactor Physics Program, including Derivation of Corrections to k_∞ in the Two-Group Approximation, Improved Experimental Capability at HTLTR, Deformation in the Vertical Safety Rods at the High Temperature Lattice Test Reactor, Measurement of k_∞ for a ThO₂-²³⁵UC₂ HTGR Lattice as a Function of Temperature, Measurement of k_∞ for a ThO₂-(²³³U,Th)O₂-C HTGR Lattice as a Function of Temperature, Design of MSBR Experiment in the HTLTR, Room Temperature Measurements on a MSBR Lattice in the HTLTR, a ThO₂-PuO₂ HTGR Experiment in HTLTR, Status of ENDF/B Cross Sections for HTLTR Studies, Review of the ENDRF/B Description of Carbon; (3) Phoenix Studies, including Evaluation of Calculational Methods Used for the Phoenix Burnup Experiment, and Phoenix Fuel Studies; (4) Steady State and Transient Subchannel Code Development and Data Analysis, including COBRA-III Computer Program, and Experimental Study of Flow Structure in Rod Bundles; (5) Plutonium Criticality Studies, including Critical Experiments with Undermoderated Mixtures of PuO₂-UO₂, and The Effect of Fixed and Soluble Nuclear Poisons on Criticality; (6) Calculations of Potential Environmental Radiological Consequences of Reactor Accidents; (7) Nuclear Graphite, including In-Reactor Creep, Radiolytic Reactions in Graphite Moderate Reactors, Effect of Sample Size on Dimensional Stability of Graphite, High Temperature Irradiations, and Mechanism of Irradiation Damage; (8) ATR 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-25-048235
• OSTI ID: 4703785
• Report Number(s): BNWL-1522-2
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACCIDENTS-- FUEL PARTICLES-- PERFORMANCE-- PLUTONIUM OXIDES-- PRESSURIZED WATER REACTORS-- PRTR-- RADIATION EFFECTS-- REACTIVITY-- SAFETY-- URANIUM DIOXIDE
ATR
ATR-- MAINTENANCE-- OPERATION
BURNUP-- FUEL ELEMENTS-- MTR-- PERFORMANCE-- PHOENIX REACTOR-- TESTING
COBRA-III
CRITICALITY-- PLUTONIUM OXIDES-- POISONING-- URANIUM DIOXIDE
Criticality
Enrichment
Experiment
FAST NEUTRONS-- GRAPHITE-- RADIATION EFFECTS
FLUID FLOW-- FUEL ELEMENT CLUSTERS-- FUEL RODS-- HEAT TRANSFER
FUEL PARTICLES-- HTGR TYPE REACTORS-- PERFORMANCE-- RADIATION EFFECTS-- REACTIVITY-- TESTING-- THORIUM OXIDES-- URANIUM DIOXIDE
Improvement
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
Nuclear Criticality Safety Program (NCSP)
Nuclear Graphite
Nuclear Poisons
Plutonium
Quarterly Report
Radiological Consequences
Radiolytic Reactions
Reaction Rates
Reactor Accidents
Relative Reaction Rates
Theory
Undermoderation
Uranium
Utilization
Water Loop