Analysis of the Phoenix Fuel Experiments

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

DOI:https://doi.org/10.2172/4097705· OSTI ID:4097705

Heeb, C. M. ^[1]

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

A depletion experiment of a plutonium-aluminum-alloy fueled core in the Materials Testing Reactor (MTR) was completed in the first half of 1970. The supporting integral experiments and the installed neutronic behavior of this "Phoenix core" are described briefly. The analysis of these experiments is described in detail. It was found that increasing the absorption of the 1 eV ²⁴⁰Pu resonance to agree with measured k_∞ value results in eigenvalues which are within 1% of the experimental values over a range ²⁴⁰Pu concentrations from 8% to 23%. The observed reactivity time behavior of the core shows a more abrupt loss of reactivity with time than had been calculated. A method of partitioning the computed reactivity time slope is presented which defines the contribution each burnable isotope makes to the total slope. A comparative analysis of two methods plus nuclear data is carried out using this technique to illustrate the complexities involved in burnup analysis. The combination of integral experiments and the experiment conducted in the MTR with the Phoenix core is a unique fund of observational knowledge on a neutronic behavior of cores containing only plutonium which can be used to test analysis methods in the absence of interference from uranium isotopes.

• 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-25-003902
• OSTI ID: 4097705
• Report Number(s): BNWL-1514
• 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
ALUMINUM ALLOYS
Analysis
BURNUP
CRITICALITY
Criticality
Experiments
FUEL ELEMENTS
MTR
Materials Testing Reactor
N38550* --Research & Test Reactors & Critical Assemblies-- Fuels
Nuclear Criticality Safety Program (NCSP)
PERFORMANCE
PLUTONIUM ALLOYS
Phoenix Core
REACTIVITY
REACTOR CORE
RESEARCH REACTORS
Safety
Uranium Isotopes