Validity of the linearity assumption in the LEPRICON adjustment module

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

OSTI ID:552567

Picavet, O; Abderrahim, H A ^[1]; Risch, P ^[2]

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1. SCK/CEN, Mol (Belgium)
2. Electricite de France, Clamart (France)

The LEPRICON adjustment module is part of the entire LEPRICON code system. It implements a least-squares method to obtain the best estimate of the neutron flux spectrum at the pressure vessel inner surface and at T/4 with their uncertainties. The LEPRICON module combines the measured and calculated activities at the surveillance location of the studied reactor together with similar results from a benchmark experiments data-base. The benchmark database contains 37 integral experiments: reaction rates of radiometric and fissile dosimeters with different threshold responses measured in Pool Critical Assembly, Pool Side Faculty, and ISNF {sup 235}U fission spectrum standard fields and National Institute of Standards and Technology {sup 252}Cf fission spectrum standard fields as well as the same calculated values using the ELXSIR and DORT tools. The LEPRICON module also takes into account 24 differential nuclear data sets (partial cross sections used in the transport calculation, fission spectrum, and dosimetry cross sections) considered to be the most important data in the transport and dosimetry calculations. The dependency between the integral experiment adjustments and those in the differential parameters is assumed to be linear; i.e., the propagation is calculated in relation to sensitivity matrices.

• OSTI ID: 552567
• 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
CROSS SECTIONS
L CODES
NEUTRON FLUENCE
NEUTRON FLUX
PRESSURE VESSELS
PWR TYPE REACTORS