NUFACE: An interface code for the calculation of nuclear responses
- Oak Ridge National Lab., TN (USA)
- Tennessee Univ., Knoxville, TN (USA)
The NUFACE interface code computes nuclear responses for use in the nuclear analysis of a given tokamak reactor design. The NUFACE code operates on the neutron and gamma fluxes provided by the one-dimensional neutral-particle transport code ONEDANT. Zonewise and zone-boundary responses are computed to obtain both zone-integrated values and maximum surface values. Information on each material mixture within a zone and on each element or isotope constituent of each material is computed. This feature allows for a detailed analysis of the reactor whereby one can easily identify the fractional contribution to the response of interest from each material and each element or isotope. 4 refs., 4 figs., 3 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 7223778
- Report Number(s):
- ORNL/FEDC-90/2; ON: DE90008088; TRN: 90-008233
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
TOKAMAK DEVICES
PHYSICAL RADIATION EFFECTS
ATOM TRANSPORT
COMPUTER ARCHITECTURE
DAMAGING NEUTRON FLUENCE
FIRST WALL
GAMMA RADIATION
N CODES
NEUTRON FLUX
RADIATION PROTECTION
RESPONSE FUNCTIONS
SHIELDING
CLOSED PLASMA DEVICES
COMPUTER CODES
ELECTROMAGNETIC RADIATION
FUNCTIONS
IONIZING RADIATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUENCE
RADIATION EFFECTS
RADIATION FLUX
RADIATION TRANSPORT
RADIATIONS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
700201* - Fusion Power Plant Technology- Blanket Engineering
990200 - Mathematics & Computers
700209 - Fusion Power Plant Technology- Component Development & Materials Testing