Effect of three cross-section libraries on the calculated neutron flux in the cavity of a PWR

Journal Article · Mon Dec 30 23:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:426494

Laky, P G ^[1]; Tsoulfanidis, N ^[2]

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1. Military Academy, West Point, NY (United States)
2. Univ. of Missouri, Rolla, MD (United States)

The objective of this study was to compare calculations of pressure vessel surveillance dosimetry foil reaction rates computed using the ENDF/B-VI cross-section libraries for all reactor core and in-vessel materials except the reactor pressure vessel for which the ENDF/B-V, ENDF/B-VI, and LANL T-2 iron cross sections were substituted. Reaction rates for dosimetry foils in the cavity surrounding the pressure vessel of a pressurized water reactor were determined using the MCNP4A code. These calculations were compared to measured reaction rates from dosimetry foil experiments conducted during cycle 10 of Arkansas Nuclear One unit 1 (ANO-1).

• OSTI ID: 426494
• Report Number(s): CONF-961103--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN TANSAO; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
NEUTRON DOSIMETRY
PRESSURE VESSELS
PWR TYPE REACTORS