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Reactivity worths of two perpendicular control mechanisms in a large graphite-moderated reactor

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6387073
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In a nuclear reactor, one of the more difficult tasks is evaluating control system worth where such systems are orthogonal to the fuel charges. Only complex, multidimensional analysis tools such as Monte Carlo techniques can provide answers for such complex reactor geometries. This paper discusses the successful application of the Monte Carlo neutron-proton (MCNP) code to control system worth evaluations for the N Reactor. The graphite-moderated, light-water-cooled Hanford site N reactor, operated by Westinghouse Hanford Company for the US Department of Energy, has a very complex geometric arrangement of horizontal pressure tubes, control rods, and ball backup safety system channels. The availability of the Hanford site version of the MCNP code enabled the set-up of numerical experiments for the N reactor lattice. Explicit representation of the entire N reactor core by Monte Carlo methods requires even larger and faster computers than are currently in use. This paper presents newly developed meter-cube model or hypercell model for MCNP analyses. The degree of representation that this model renders for the whole reactor core and the extent of the capability that this model could simulate under a variety of operational conditions are the subject of the discussion here. The reactivity worths of the two perpendicular control systems (control rods and safety ball channels) are specifically considered, neither of which has been explicitly calculated before with one code.
OSTI ID:
6387073
Report Number(s):
CONF-891103--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
Country of Publication:
United States
Language:
English

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BORON
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
CONTROL SYSTEMS
ELEMENTS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
GRAPHITE MODERATED REACTORS
HANFORD RESERVATION
KINETICS
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NEUTRON ABSORBERS
NEUTRON TRANSPORT
PLUTONIUM PRODUCTION REACTORS
POWER REACTORS
PRESSURE TUBES
PRODUCTION REACTORS
RADIATION TRANSPORT
REACTIVITY WORTHS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR KINETICS
REACTOR SAFETY
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SEMIMETALS
SIMULATION
TUBES
US DOE
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US ORGANIZATIONS
WATER COOLED REACTORS