Published 1993
| Version v1
Journal article
NESTLE: A nodal kinetics code
- 1. North Carolina State Univ., Raleigh (United States)
- 2. Los Alamos National Lab., NM (United States)
- 3. Electricite de France, Clamart (France)
Description
The NESTLE nodal kinetics code has been developed for utilization as a stand-alone code for steady-state and transient reactor neutronic analysis and for incorporation into system transient codes, such as TRAC and RELAP. The latter is desirable to increase the simulation fidelity over that obtained from currently employed zero- and one-dimensional neutronic models and now feasible due to advances in computer performance and efficiency of nodal methods. As a stand-alone code, requirements are that it operate on a range of computing platforms from memory-limited personal computers (PCs) to supercomputers with vector processors. This paper summarizes the features of NESTLE that reflect the utilization and requirements just noted
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 68
- Journal Page Range
- p. 432.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) annual meeting.
- Dates
- 20-24 Jun 1993.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25022421
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FINITE DIFFERENCE METHOD; N CODES; NEUTRON DIFFUSION EQUATION; NUMERICAL SOLUTION; REACTOR CORES; REACTOR KINETICS EQUATIONS; REACTOR PHYSICS; REACTORS; WATER COOLED REACTORS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; EQUATIONS; ITERATIVE METHODS; REACTOR COMPONENTS; SIMULATION
Optional Information
- Secondary number(s)
- CONF-930601--.