Fast neutron exposure calculations for the surveillance capsules of a boiling water reactor
- Pennsylvania State Univ., University Park (United States)
The aim of any reactor pressure vessel (RPV) surveillance program is to monitor the neutron-induced material degradation of the RPV wall and to provide data periodically for adjustment of certain operational parameters to ensure continued safe operation. Surveillance capsules are usually installed in nuclear power plants prior to startup so that they attain higher fast fluence exposure than that of the RPV wall peak position. This paper calculates the surveillance capsule lead or lag factor for a currently operating boiling water reactor (BWR) (designated as REACTOR-B) using two neutron cross-section libraries (SAILOR and ELXSIR). In addition, the total displacement per atom (dpa) through the pressure vessel wall is compared with that of the fast flux and with the attenuation functions given in US Nuclear Regulatory Commission Guide 1.99, Revs. 1 and 2. A detailed synthesized three-dimensional transport analysis was performed and American Society for Testing and Materials standards were followed to the extent practical.
- OSTI ID:
- 5818703
- Report Number(s):
- CONF-930601-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
PRESSURE VESSELS
PHYSICAL RADIATION EFFECTS
RADIATION MONITORING
FAST NEUTRONS
NUCLEAR POWER PLANTS
SAFETY
BARYONS
CONTAINERS
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
FERMIONS
HADRONS
MONITORING
NEUTRONS
NUCLEAR FACILITIES
NUCLEONS
POWER PLANTS
POWER REACTORS
RADIATION EFFECTS
REACTORS
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
220900 - Nuclear Reactor Technology- Reactor Safety