NEWLIT - a general code for neutron wall loading distribution in toroidal reactors
Creators
- 1. Fusion Technology Institute, University of Wisconsin, Madison, WI
Description
A computer program for evaluating the poloidal distribution of the neutron wall loading (NWL) in toroidal fusion reactors is developed using numerical integration for general plasma and wall shapes. The neutron source within the plasma could be uniform or could be described to properly represent the neutron density associated with the magnetic flux surfaces. The method and techniques used in NEWLIT are presented. A comparison with the Monte-Carlo code MCNP shows excellent agreement with substantial savings in computer time and required user time. To verify the validity of the NWL as calculated by NEWLIT, a detailed 3-D neutronics calculation was carried out for a representative tokamak reactor. The poloidal distribution of the important responses is compared to the NWL poloidal distribution
Additional details
Publishing Information
- Journal Title
- Fusion Technol.
- Journal Volume
- 8
- Journal Issue
- 1
- Series
- Fusion Technol.
- Journal Page Range
- 608-613
- ISSN
- 0748-1896
- CODEN
- FUSTE
Conference
- Title
- 6. topical meeting on the technology of fusion energy.
- Dates
- 3-7 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17075168
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; DISTRIBUTION; FIRST WALL; FLUX DENSITY; MAGNETIC FLUX; N CODES; NEUTRON FLUENCE; NEUTRON FLUX; THERMONUCLEAR REACTORS; THREE-DIMENSIONAL CALCULATIONS; TOKAMAK DEVICES; WALL LOADING
- Descriptors DEC
- CLOSED PLASMA DEVICES; POWER DENSITY; RADIATION FLUX; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS
Optional Information
- Secondary number(s)
- CONF-850310--.