Technical Activities Quarterly Report: AEC Reactor Development and Technology Program (April, May, June 1971)

Technical Report · Fri Oct 01 00:00:00 EDT 1971

DOI:https://doi.org/10.2172/4730151· OSTI ID:4730151

Schmid, L. C. ^[1]

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

Udpates include: (1) Defect Testing; (2) High Temperature Reactor Physics, including Reactivity Measurements in a Mockup MSBR Lattice in the HTLTR, Measurement of Neutronic Parameters for a ThO₂-PuO₂ HTGR Lattice in the HTLTR; (3) Steady State and Transient Subchannel Code Development and Data Analysis, including COBRA-III Computer Program, and Experimental Study of Flow Structure in Rod Bundles; (4) The Effect of Soluble Nuclear Poisons on Criticality; (5) Nuclear Graphite, including In-Reactor Creep, Radiolytic Reactions in Graphite Moderated Reactors, Effect of Sample Size on Dimensional Stability of Graphite, High Temperature Irradiations, and Mechanism of Irradiation Damage.

• 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-26-001548
• OSTI ID: 4730151
• Report Number(s): BNWL-1522-3
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-72
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
36 MATERIALS SCIENCE
CARBON DIOXIDE
CARBON MONOXIDE
COOLANT LOOPS
CRITICALITY
EXPANSION
FAILURES
FAST NEUTRONS
FUEL CANS
FUEL ELEMENTS
GADOLINIUM
GRAPHITE
GRAPHITE MODERATED REACTORS
HELIUM
HTGR TYPE REACTORS
HTLTR
HYDROGEN
MIXTURES
MOCKUP
MSBR
PERFORMANCE
PLUTONIUM NITRATES
PLUTONIUM OXIDES
POISONING
PRODUCTION
RADIATION EFFECTS
RADIOLYSIS
REACTIVITY WORTHS
REACTOR KINETICS
REACTOR LATTICES
THORIUM OXIDES
VAPORS
WATER
ZIRCALOY
Nuclear Criticality Safety Program (NCSP)
Criticality
Safety
Quarterly Report
COBRA-III
Fuel Elements
Fast Neutrons
Expansion
In-Reactor Creep
Plutonium Oxides
Poisoning
Reactivity
Radiolysis
Production
Reactor Kinetics
Nuclear Graphite
Defect
Testing
Physics
Measurements
Mockup
N38100* -Power Reactor Development
N20330 -Chemistry- Radiation & Nuclear Chemistry-Radiolysis
N30250 -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects