Category Archives: WORKSHOP ON NUCLEAR REACTION DATA AND. NUCLEAR REACTORS:. PHYSICS, DESIGN AND SAFETY

Segment 4: OPTICAL

The optical model parameter (OMP) segment is provided in two forms: full library (archival form) and shorter library with all single-energy potentials removed (user file). Currently, the user (archival) file contains 258 (258) po­tentials for incident neutrons, 98 (143) potentials for incident protons, 8 (11) for deuterons, 1 (26) for tritons, 3 (53) for 3He particles, and 10 (10) for […]

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Nuclear applications

The US ENDF/B-VI nuclear data library was released to the international community in the early 1990s (Dunford, 1992). An initial point of note is the development over many years of an internationally-accepted data format (ENDF-6), including the potential to accommodate uncertainties in the form of covariance matrices. Specific aims included the production of a self-consistent set of evaluated neutron cross […]

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Thermo-chemical Water Splitting

One mechanism that is being considered seriously for hydrogen production is thermo-chemical water splitting by the Iodine-Sulfur (IS) process. The IS process was originally proposed by the General Atomic Company in early 1970’s and is very promising because it involves only a few reaction steps. In this process Hydrogen — Iodide (HI) is produced by a cyclic chemical reaction chain […]

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Neutron Cross Sections

Uncertainties in the neutron-absorption cross sections of the fission products have only a marginal effect on decay-heat predictions for cooling times < 104 sec. Changes in decay heat at longer cooling times are dependent on the flux level and irradiation time, and no simple estimate can be made of the uncertainty in decay heat at these cooling times that arises […]

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Institute for Transuranium Elements (ITU), Karlsruhe, Germany

‘Nuclides 2000: an Electronic Chart of the Nuclides’ has been developed and released as a CD-ROM by ITU, Karlsruhe. The Nuclide explorer gives access to the radionuclide decay data from JEF-2.2, using either a “Chart of the Nuclides’ or Segre display (Magill, 1999). Derived data include activities, gamma dose rates and annual limits of intake. There are additional features to […]

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Asymptotic contributions of the Hamiltonian

In order to determine the reaction matrix amn from eq. (2.24) and eq. (2.31) we need the matrix elements of H between regular and irregular Coulomb functions. Hence, we need matrix elements of H, eq. (2.18 — 2.19) between Fl, Gl and rv, respectively. Since FL and GL are not square-integrable functions, some care is necessary. In the discussion below […]

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Liquid Metal-cooled Reactors

There has been renewed interest in recent years in liquid metal cooled reactors particularly for smaller sized designs and from a sustainable development point of view. They are significant because they can breed new fissile material and extend the potential of nuclear energy. Because of their fast neutron spectrum, which can be used as a burner or a breeder, they […]

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