PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR JULY 1, 1958- SEPTEMBER 30, 1958

Technical Report · Wed Oct 15 04:00:00 EDT 1958

OSTI ID:4262341

Preliminary design data for the reactor with a nuclear superheater are given. The fuel element cladding material has been designated as X 8001 aluminum alloy. Corrosion testing of X 8001 is described. Welding experiments of end caps of several designs were conducted. A new core layout is described. Modifications to the boiler fuel elements are discussed. The reactor vessel design was revised slightly. Progress on some of the more impontant design elements is discussed. A preliminary stress analysis was made of the lower head design. The first silicone rubber seal was tested to failure and the test history is given. A piping flexibility analysis fur recirculation piping was performed. Modifications to the recirculation pumps are described. The thermal conatants, microscopic cross sections, and diffusion coefficient were calculated fer various core regions utilizing the Sufocate code. A study is presently being made to determine the effect of irradiation history on reactivity, power and void distributions, and isotopic densities of various elements so that core lifetime, control reqzirements, and reloading schedules may be established. An experiment is described to measure the reactivity change caused by flooding of the steam passages of the superheater elements with moderator. Using a preliminary layout for the turbine building, dose rates nt various positions were calculated. The investigation of system stability required for the Preliminary Safeguards Report was completed. A test was conducted to determine the effect of a power excursion in the critical facility reactor on the void simulator material. Startup and shutdown procedures are listed. (For preceding period see AECU-3782.) (W.D.M.)

• Research Organization: Allis-Chalmers Mfg. Co. Nuclear Power Div., Milwaukee
• NSA Number: NSA-13-004258
• OSTI ID: 4262341
• Report Number(s): AECU-3910; ACNP-5812
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM ALLOYS
ANALOG SYSTEMS
BUILDINGS
BURNUP
CANNING
CONFIGURATION
CONTROL ELEMENTS
COOLANT LOOPS
COOLING
CORROSION
CRBR
CRITICAL ASSEMBLIES
CROSS SECTIONS
DENSITY
DIFFUSION LENGTH
EQUATIONS
EXCURSIONS
FAILURES
FISSION PRODUCTS
FUEL ELEMENTS
HEAT TRANSFER
IRRADIATION
ISOTOPES
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MODERATORS
NEUTRON FLUX
NUMERICALS
OPERATION
PIPES
PLANNING
POISONING
POWER PLANTS
PRESSURE
PRESSURE VESSELS
PROGRAMMING
PUMPS
RADIATION DOSES
RADIATION PROTECTION
REACTIVITY
REACTOR CORE
REACTOR FUELING
REACTOR SAFETY
REACTORS
RUBBER
SEALS
SHU