Fusion power plant performance analysis using the HERCULES code
Creators
- 1. EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom) and University of Birmingham, School of Physics and Astronomy, Edgbaston, Birmingham B15 2TT (United Kingdom)
- 2. EURATOM/UKAEA Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)
Description
The HERCULES code was developed to assist in the safety and environmental analysis tasks of the European Power Plant Conceptual Study (PPCS). Its capabilities, however, extend beyond this kind of assessments. Coupling of the different computational tools and nuclear databases to the same geometry and material compositions, automation of input file generation and post-processing subroutines enable self-consistent calculations and radial-poloidal analyses of several parameters of interest in fusion technology design, optimising time and computer resources. Results include 2D variations of the neutron flux distribution and energy spectra, material activation and related quantities, wall loading, nuclear primary heating, tritium and helium production and radiation damage rates to materials. The capabilities of the neutron transport module of HERCULES are presented here and benchmarked on the PPCS models. Results are consistent with values assumed in the design process or obtained through the more specific PPCS analyses: tritium generation ratios are in the range between 1.12 and 1.36, energy multiplication between 1.16 and 1.39, and average wall loads between 1.90 and 2.54 MWm-2. Issues related to tritium breeding and possible tungsten first wall coating of the near-term models are discussed
Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2005.09.054;
- PII
- S0920-3796(05)00650-2;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 81
- Journal Issue
- 8-14
- Journal Page Range
- p. 1231-1237
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 7. international symposium on fusion nuclear technology
- Acronym
- ISFNT-7
- Dates
- 22-27 May 2005
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37109459
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; COUPLING; DESIGN; DISTRIBUTION; ENERGY SPECTRA; FIRST WALL; GEOMETRY; H CODES; HELIUM; NEUTRON FLUX; NEUTRON TRANSPORT; PERFORMANCE; THERMONUCLEAR POWER PLANTS; THERMONUCLEAR REACTOR MATERIALS; TRITIUM; TUNGSTEN; WALL LOADING
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; COMPUTER CODES; ELEMENTS; FLUIDS; GASES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MATERIALS; MATHEMATICS; METALS; NEUTRAL-PARTICLE TRANSPORT; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; POWER DENSITY; POWER PLANTS; RADIATION FLUX; RADIATION TRANSPORT; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; REFRACTORY METALS; SPECTRA; THERMAL POWER PLANTS; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENTS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.