Differential and double differential cross sections for neutron induced reactions on Cr, Fe & Ni based on TALYS 1.9

dc.contributor.advisorPandey, Bhawna
dc.contributor.authorBhatt, Kavita
dc.date.accessioned2019-02-01T10:17:51Z
dc.date.available2019-02-01T10:17:51Z
dc.date.issued2018-07
dc.description.abstractSustainable development requires international cooperation and the effective use of technology. The factors contributing to the continuing interest in nuclear power include increasing global demand for energy, as well as concerns about climate change, increasing fossil fuel prices and security of energy supply. There are revolutionary possibilities in the development of fusion reactors. Fusion power offers the prospect of a long-term efficient energy production. Neutron cross-section data are the backbone for the designing of the critical component of fusion reactor. Complete set of neutron cross-section data is one of the urgent requisites for the successful operation of the upcoming fusion reactor. Out of the all the neutron induced reactions, the ones that produce gases are of utmost importance. The generation of hydrogen and helium gases are mainly through (n,p) ( n, n’p), (n,_), (n, n’_) reactions. These reactions are induced on the first wall, structural and blanket components of the reactor. In addition to the production of hydrogen and helium, the other processes such as atomic displacements and transmutations, etc., can produce micro structural defects and damage physical properties of the material. The materials suitable for the reactor structures are stainless steel with Cr, Fe and Ni as the main constituents. Very less experimental data is available for DX and DDX in EXFOR nuclear data library. The main reason can be attributed to the experimental difficulties, such as background counts, detector resolution, particle discrimination, relatively small values of nuclear cross-sections, etc. The present investigation is carried out to find the differential cross-section (DX) and double differential cross-section (DDX) values of Cr, Fe and Ni for (n,xp) and (n,x_) reactions at neutron energy 14.1 and 14.6MeV using TALYS-1.9. The contributions from direct, pre-equilibrium and compound nucleus processes to the total reaction are studied along with the study of all the open reaction channels for (n,xp) and (n,x_) reaction.en_US
dc.identifier.urihttp://krishikosh.egranth.ac.in/handle/1/5810093269
dc.keywordsneutron, chromium, iron, nickelen_US
dc.language.isoenen_US
dc.pages104en_US
dc.publisherG.B. Pant University of Agriculture and Technology, Pantnagar - 263145 (Uttarakhand)en_US
dc.research.problemNuclear Energyen_US
dc.subPhysicsen_US
dc.subjectnullen_US
dc.themePhysicsen_US
dc.these.typeM.Scen_US
dc.titleDifferential and double differential cross sections for neutron induced reactions on Cr, Fe & Ni based on TALYS 1.9en_US
dc.typeThesisen_US
Files
Original bundle
Now showing 1 - 1 of 1
Loading...
Thumbnail Image
Name:
KavitaBhatt.pdf
Size:
17.4 MB
Format:
Adobe Portable Document Format
Description:
License bundle
Now showing 1 - 1 of 1
No Thumbnail Available
Name:
license.txt
Size:
1.71 KB
Format:
Item-specific license agreed upon to submission
Description:
Collections