Flux and fluence determination using the material scrapings approach

Conference · Wed Jan 01 00:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7145471

Basha, H S; Manahan, M P ^[1]

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1. Pennsylvania State Univ., University Park (United States)

The conventional approach to flux determination is to use high-purity dosimeters to characterize the neutron field. This paper presents an alternative approach called the scraping method. This method consists of taking scraping samples from an in-service component and using this material to measure the specific activity for various reactions. This approach enables the determination of the neutron flux and fluence incident on any component for which small chips of material can be safely obtained. It offers a capability for determining the neutron flux for components such as reactor internals without destructively removing them from service. The scrapings methodology was benchmarked by comparison with the results obtained using conventional dosimetry data from the San Onofre nuclear generation station Unit 2 (SONGS-2). Additionally, since the goal of any reactor physics analysis is to reduce uncertainty to the extent practical, it is important that the best available cross-section library be used. The fast flux calculated-to-experimental (C/E) ratios at the SONGS-297-deg in-vessel surveillance capsule and the REACTOR-X 90-deg ex-vessel dosimetry positions were studied for several cross-section libraries, including BIGLE-80, SAILOR, and ELXSIR. REACTOR-X is a pressurized water reactor power plant currently operating in the US.

• OSTI ID: 7145471
• Report Number(s): CONF-920606-; CODEN: TANSA
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 65; Conference: American Nuclear Society annual meeting, Boston, MA (United States), 7-12 Jun 1992; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR INTERNALS
NEUTRON DOSIMETRY
SAMPLING
SAN ONOFRE-2 REACTOR
REACTOR PHYSICS
BENCHMARKS
CHARPY TEST
CROSS SECTIONS
DECONTAMINATION
NEUTRON FLUENCE
NEUTRON FLUX
NEUTRON SPECTRA
PRESSURE VESSELS
SURVEILLANCE
THREE-DIMENSIONAL CALCULATIONS
CLEANING
CONTAINERS
DESTRUCTIVE TESTING
DOSIMETRY
ENRICHED URANIUM REACTORS
IMPACT TESTS
MATERIALS TESTING
MECHANICAL TESTS
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
RADIATION FLUX
REACTOR COMPONENTS
REACTORS
SPECTRA
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled