Scheme for Burn-Up Calculations. IV. Exchange of the Fuel from the Axis to the Boundary of a Cylindrical Reactor FO Finite Height (in German)
Journal Article
·
· Kernenergie (Berlin)
OSTI ID:4074147
- Wissenschaftlich-Technisches Büro für Reaktorbau (WTBR), Berlin (Germany)
The burn-up after the transfer of the fuel rods from the axis to the perimeter of a reactor of finite height is calculated. The discrete transfer pattern through a continuous passage of the fuel was approximated. The one-group theory was used. It was assumed that k, is linearly dependent on the thermal neutron flux. Expressions for the maximum and mean burn-up depth and estimations of the neutron flux inhomogeneities to be expected are derived.
- Research Organization:
- Wissenschaftlich-Technisches Büro für Reaktorbau (WTBR), Berlin (Germany)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-15-020341
- OSTI ID:
- 4074147
- Journal Information:
- Kernenergie (Berlin), Journal Name: Kernenergie (Berlin) Vol. 4; ISSN 0023-0642
- Country of Publication:
- Germany
- Language:
- German
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