Neutron flux at the PV of a PWR determined with the MCNP code
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:89227
- Univ. of Missouri, Rolla, MO (United States)
The Monte Carlo neutral particle code (MCNP4a) was used to determine the neutron energy spectrum at the pressure vessel and reaction rates for dosimetry foils in the cavity surrounding the pressure vessel of a pressurized water reactor (PWR). Using plant-measured data for power distribution as input, this work yielded accurate computed neutron flux at the pressure vessel, as verified by good agreement between computed and measured dosimetry foil reaction rates. No normalization factors other than the total neutron source were introduced.
- OSTI ID:
- 89227
- Report Number(s):
- CONF-941102--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
Cadmium cutoff energy for MCNP modeling of dosimetry reactions
Effect of three cross-section libraries on the calculated neutron flux in the cavity of a PWR
Neutron fluence at the pressure vessel of a pressurized water reactor determined by the MCNP code
Journal Article
·
Sat Oct 01 00:00:00 EDT 1994
· Nuclear Science and Engineering; (United States)
·
OSTI ID:7192230
Effect of three cross-section libraries on the calculated neutron flux in the cavity of a PWR
Journal Article
·
Mon Dec 30 23:00:00 EST 1996
· Transactions of the American Nuclear Society
·
OSTI ID:426494
Neutron fluence at the pressure vessel of a pressurized water reactor determined by the MCNP code
Journal Article
·
Tue Oct 31 23:00:00 EST 1995
· Nuclear Science and Engineering
·
OSTI ID:163182