HELIOS verification using PWR critical experiments loaded with MOX fuels

Journal Article · Mon Dec 01 04:00:00 EST 1997 · Transactions of the American Nuclear Society

OSTI ID:552583

Kim, Taek Kyum; Joo, Hyung Kook; Kim, Young Jin ^[1]

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1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

As a participant in the VIPEX-pressurized water reactor (PWR) international program organized by Belgonucleaire and CEN-SCK (Belgium), Korea Atomic Energy Research Institute had the opportunity to verify the neutron and gamma transport code HELIOS against a PWR critical experiment loaded with high-plutonium-content mixed-oxide (MOX) fuels. Two mock-ups, ALL-MOX and GD-MOX, were investigated at the VENUS critical facility, which consisted of typical 17 X 17 PWR fuel assemblies, driver, and water reflector regions. In the ALL-MOX mock-up core, a standard MOX assembly was loaded at the center of the core, which was surrounded by four UO{sub 2} fuel assemblies. In the GD-MOX mock-up core, the central MOX assembly was replaced with a GD-MOX fuel assembly. Therefore, the only difference between the ALL-MOX and the GD-MOX mock-up was the existence of 20 UO{sub 2} fuel rods bearing Gd{sub 2}O{sub 3} in the central assembly, which made the critical water level higher. For the simulation of a hot-full-power (HFP) moderator condition at room temperature, aluminum microtubes and -rods were inserted into MOX and UO{sub 2} fuel assemblies, respectively. In each mock-up, the critical water level, reactivity effect of water level, axial bucklings, horizontal rodwise fission rate distribution, and detector responses were measured. The horizontal rodwise fission rate distribution was inferred from gamma scanning data.

• OSTI ID: 552583
• Report Number(s): CONF-971125--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
66 PHYSICS
CRITICALITY
FUEL ASSEMBLIES
FUEL RODS
H CODES
MIXED OXIDE FUELS
NEUTRON TRANSPORT
PWR TYPE REACTORS
VERIFICATION