Evaluation of displacement cross-section for neutron-irradiated 15-15Ti steel and its swelling behavior in CiADS radiation environment
- 1. School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing (China)
- 2. Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou (China)
- 3. Paul Scherrer Institute, Villigen (Switzerland)
Description
Highlights: • Method to calculate displacement cross-section in NRT and arc-dpa models. • Calculation of displacement cross-section for several steels used worldwide. • Evaluation of 15-15Ti steel failure lifetime due to swelling in CiADS core. - Abstract: We report on the proposed method of evaluating the displacement cross-sections in NRT and BCA-arc-dpa models. The method is based on the NJOY code in conjunction with the IOTA code and is applicable to neutron energy in the range of 0.1 neV–20 MeV, defined by using NJOY and nuclear library files with data up to 20 MeV. The displacement cross-section has been calculated for natural iron, 15-15Ti, 316L, Eurofer, ODS, and T91 steels. The displacement cross-sections for 15-15Ti steel were used to estimate radiation damage and swelling level under irradiation conditions of the China Initiative Accelerator Driven System (CiADS) subcritical core. The swelling analysis has shown, that in CiADS radiation environment, the 15-15Ti steel has a good margin to cladding failure due to swelling and, therefore, might be a cladding material for CiADS.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2019.07.035Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2019.07.035;
- PII
- S0306454919304207;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 133
- Journal Page Range
- p. 937-949
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51008028
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- ACCELERATOR-DRIVEN TRANSMUTATION FACILITIES; CARRIER LIFETIME; CHINA; CROSS SECTIONS; FAILURES; FERRITIC STEELS; IRON; MARTENSITIC STEELS; MEV RANGE; NEUTRONS; NUCLEAR DATA COLLECTIONS; RADIATION EFFECTS; STAINLESS STEEL-316L; SWELLING
- Descriptors DEC
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; ALLOYS; ASIA; AUSTENITIC STEELS; BARYONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; DEFORMATION; ELEMENTARY PARTICLES; ELEMENTS; ENERGY RANGE; EXPERIMENTAL REACTORS; FERMIONS; HADRONS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; METALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NUCLEONS; REACTORS; RESEARCH AND TEST REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEELS; SUBCRITICAL ASSEMBLIES; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS
Optional Information
- Notes
- © 2019 Elsevier Ltd. All rights reserved.