A WIMS-NESTLE reactor physics model for an RBMK reactor
- Los Alamos National Lab., NM (United States)
- Pacific Northwest National Lab., Richland, WA (United States)
This work describes the static neutronic calculations made for a three-dimensional model of an RBMK (Russian) reactor. Future work will involve the use of this neutronic model and a thermal-hydraulic model in coupled calculations. The lattice code, WIMS-D, was used to obtain the cross sections for the static neutronic calculations. The static reactor neutronic calculations were made with NESTLE, a three-dimensional nodal diffusion code. The methods used to establish an RBMK reactor model for use in these codes are discussed, and the cross sections calculated are given.
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 266875
- Report Number(s):
- LA-UR--96-1935; CONF-960924--1; ON: DE96012737
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results of comparative RBMK neutron computation using VNIIEF codes (cell computation, 3D statics, 3D kinetics). Final report
Deterministic modelling of the SPERT IV reactor transients using the multi-physics capability of WIMS
Validation of HELIOS Neutron Cross-Section Library for RBMK Reactors Against the Data From the Critical Facility Experiments
Technical Report
·
Sat Dec 30 23:00:00 EST 1995
·
OSTI ID:219464
Deterministic modelling of the SPERT IV reactor transients using the multi-physics capability of WIMS
Conference
·
Fri Jul 01 00:00:00 EDT 2022
·
OSTI ID:23203902
Validation of HELIOS Neutron Cross-Section Library for RBMK Reactors Against the Data From the Critical Facility Experiments
Conference
·
Mon Jul 01 00:00:00 EDT 2002
·
OSTI ID:21072796