Published March 1986
| Version v1
Journal article
Irradiation damage calculation of PWR pressure vessel and analysis of cross section sensitivity
Description
This paper gives the results of the flux and atomic displacement calculations for Fort Calhoun Reactor in one-dimentional models. A comparison between calculated and measured maximum fast neutron dose on the inner surface of the pressure vessel shows good agreement. Cross section sensitivity studies of radiation influence on the pressure vessel shows that the cross sections of H, Fe and O are most important, and those of Cr, Ni, 238U and Zr are of secondary importance whereas the cross sections of isotopes like 235U are not important. At the inner surface of the pressure vessel about 70% of the total displacements are produced by fast neutrons with energies greater than 1 MeV
Additional details
Publishing Information
- Journal Title
- Chin. J. Nucl. Sci. Eng.
- Journal Volume
- 6
- Journal Issue
- 1
- Series
- Chin. J. Nucl. Sci. Eng.
- Journal Page Range
- 51-59
- CODEN
- HYGOD
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 18057593
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; ATOMIC DISPLACEMENTS; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; D CODES; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; PWR TYPE REACTORS; S CODES; TOTAL CROSS SECTIONS
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; CROSS SECTIONS; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; RADIATION EFFECTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS