Critical Experiments in an MTR Mockup Using Phoenix Fuel

Technical Report · Mon Jun 01 04:00:00 EDT 1970

DOI:https://doi.org/10.2172/4055008· OSTI ID:4055008

Davis, Jr., E. C. ^[1]; Smith, R. I. ^[1]; Williams, L. D. ^[1]

---

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

Utilization of ²⁴⁰Pu as a convertible poison in plutonium fueled systems is being studied under the Phoenix Fuel Reactor Program at Pacific Northwest Laboratory (PNL). An extensive experimental program using Phoenix fuel in a critical mockup of the Materials Testing Reactor (MTR) has been completed in the Plutonium Recycle Critical Facility (PRCF) at PNL. The PRCF-Phoenix mockup duplicated as closely as possible the physical configuration of the MTR in order to determine the characteristics of such a core. The experiments performed in this mockup provided information on the reactivity effects and power distributions to be expected of an MTR-Phoenix fuel core prior to the loading of a full core in the MTR. These data have provided an excellent test of the computational methods currently being applied to Phoenix Fuel cores. The results of the PRCF experiments are presented in this report.

• 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-25-018170
• OSTI ID: 4055008
• Report Number(s): BNWL-1481
• 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
CONFIGURATION
CRITICALITY
Criticality
FUELS
MOCKUP
MTR
Materials Testing Reactor
Mockup
N38510* --Research & Test Reactors & Critical Assemblies-- Kinetics & Dynamics
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM 240
PRCF
Phoenix Fuel Reactor Program
Plutonium Fueled Systems
REACTIVITY
REACTOR CORE
RESEARCH REACTORS
Safety
TESTING