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Evaluation of the source spectrum effect on the calculated RPV fluence

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7056395
;  [1]
  1. Pennsylvania State Univ., University Park (United States)
Determination of the neutron fluence at the reactor pressure vessel (RPV) is necessary for reactor safety evaluation and the possibility of plant life extension. In recent years, there has been renewed activity on the development of more accurate analytical techniques and also evaluation of the nuclear data used for such calculations. To estimate the neutron fluence at the pressure vessel, transport theory calculations are performed for a model that represents the reactor core and its surrounding regions up to the concrete wall. The core is simulated by a multigroup fixed source distribution, which is evaluated in three steps: (1) a power distribution is estimated via a simulation code; (2) power is converted to the neutron source; (3) multigroup neutron source distribution with an estimated source spectrum. This paper analyzes the effect of variations of the source spectrum on the calculated activities of the in-vessel capsule and ex-vessel dosimeter for different dosimetry materials. It is worth noting that these activities when compared with the measured activities provide an adjustment factor for the calculated flux/fluence at the RPV.
OSTI ID:
7056395
Report Number(s):
CONF-920606--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
Country of Publication:
United States
Language:
English

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