Published March 2022
| Version v1
Report
Benchmark Consolidated Results Against Experimental Data from ANSTO-2. Annex II
Creators
Description
The starting point for the neutronic calculations was a 69 group nuclear data library based on the WIMS library and data from the HELIOS library. Cell calculations were performed using CONDOR for the fuel assemblies, control rods, other core components and irradiation facilities. A 3-group (thermal, epithermal and fast) cross-section library was developed using the various cell models. A one quarter two-dimensional model of a fuel assembly is shown in Fig. I‒4. It indicates the detail represented in the CONDOR model used for cross-section preparation including the fuel meat, clad, coolant, side plate and cadmium burnable wires.
Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-101222-7
- Imprint Title
- Benchmarks of Fuel Burnup and Material Activation Computational Tools Against Experimental Data for Research Reactors. Results of a Coordinated Research Project
- Imprint Pagination
- 278 p.
- Journal Page Range
- p. 80-96
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1992
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53082611
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- ANSTO; BENCHMARKS; CONTROL ELEMENTS; COOLANTS; CROSS SECTIONS; EXPERIMENTAL DATA; FUEL ASSEMBLIES; IRRADIATION PLANTS; NEUTRON TRANSPORT; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; PLATES; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- AUSTRALIAN ORGANIZATIONS; DATA; ENERGY SOURCES; FUELS; INFORMATION; MATERIALS; NATIONAL ORGANIZATIONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FACILITIES; NUMERICAL DATA; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR MATERIALS
Optional Information
- Notes
- 8 refs., 1 figs., 19 tabs.