Benchmarking TMI-2 Core and Canister Calculations

Conference · Sun Jun 15 00:00:00 EDT 1986 · Transactions of the American Nuclear Society

OSTI ID:6623742

Murray, R. L. ^[1]; Williams, D. S. ^[1]; Rommel, J. C. ^[1]

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1. North Carolina State University, Raleigh, NC (United States)

For the application of the Monte Carlo code KENO to the calculations of k/sub eff/ for Three Mile Island Unit 2 (TMI-2) fuel in various arrangements, values of code bias were required. The presumed core configuration lay outside the region for which the code has been validated. There is an abundance of critical experiment data relevant to power reactor fuel assemblies and highly enriched systems. However, there are few experiments involving high boron content and close packing of fuel as expected in the damaged core configuration. Such fuel would exhibit a harder neutron spectrum than that of most thermal power reactors. There also are few experiments involving small containers of low-enrichment UO₂ with solid internal poisons, and thus exhibiting the relatively large neutron losses due to leakage and absorption by B₄C that characterize the canisters to be used for storage of fuel removed from the reactor. The procedures for the benchmarking effort and resulting values of biases to be added to the k_eff calculated by KENO are discussed.

• Research Organization: North Carolina State University, Raleigh, NC (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 6623742
• Report Number(s): CONF-860610-; CODEN: TANSA; TRN: 87-016340
• Journal Information: Transactions of the American Nuclear Society, Vol. 52; Conference: American Nuclear Society Annual Meeting, Reno, NV (united States), 15 Jun 1986; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
CORIUM
CRITICALITY
STORAGE
REACTOR CORES
MULTIPLICATION FACTORS
THREE MILE ISLAND-2 REACTOR
REACTOR DISMANTLING
BENCHMARKS
BORON
CONTAINERS
FUEL ASSEMBLIES
K CODES
MODERATORS
MONTE CARLO METHOD
ORNL
QUANTITY RATIO
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REMOVAL
URANIUM DIOXIDE
ACCIDENTS
ACTINIDE COMPOUNDS
CHALCOGENIDES
COMPUTER CODES
DEMOLITION
ELEMENTS
ENRICHED URANIUM REACTORS
NATIONAL ORGANIZATIONS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SEMIMETALS
THERMAL REACTORS
URANIUM COMPOUNDS
URANIUM OXIDES
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
Nuclear Criticality Safety Program (NCSP)
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled