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Koeberg Surveillance Capsule Fluence Determination Using PCDC Dosimetry Cross Sections and Activation Measurements Pages: 10 Published: Jan 1994
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View License Agreement Source: STP1228-EB Abstract Neutron fluences were calculated for the first Reactor Vessel Surveillance (RVS) capsules extracted from Koeberg Unit 1 and 2. For the calculation of the Koeberg RVS-capsule dosimetry cross sections a calculational system (called PCDC) was developed on a 32-bit i386/i486 personal computer (PC). This system consists of pre- and post-processors, a 171-group neutron reaction cross section library, a 171-group reactor zone flux spectrum library and an interface with the SAND-II, DOSCROS-84 and IRDF-90 dosimetry libraries. The sensitivity of these cross sections was determined for different reactor model parameters, core conditions and dosimetry libraries. Using the IRDF-90 dosimetry library, a maximum difference of 15% was obtained between the fluences predicted with the non-fissionable dosimeters. Keywords: Reactor Vessel Surveillance, Koeberg Reactor, Neutron Fluence, Dosimetry, DOT3.5, Dosimetry Libraries Paper ID: STP15108S Committee/Subcommittee: E10.01 DOI: 10.1520/STP15108S ASTM International is a member of CrossRef. | ||