New evaluated kerma factor library from ENDF/B-V data
Conference
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· Transactions of the American Nuclear Society; (USA)
OSTI ID:6791879
The problem addressed in this paper is the accurate evaluation of neutron fluence-to-kerma (kinetic energy released in materials) factors from microscopic nuclear data. Accurate kerma factors are necessary for calculating the local heat generation in materials subject to neutron irradiation, such as shields and fusion reactor blankets. The new algorithms developed for this purpose combine in a consistent manner the two basic methods for computing kerma factors, namely, reaction kinematics and direct energy balance. These algorithms are implemented in the code KAOS-V (kerma and other stuff), which was used as the main evaluating tool to construct the nuclear response function library KAOS/LIB-V.
- OSTI ID:
- 6791879
- Report Number(s):
- CONF-890604-; CODEN: TANSA; TRN: 90-023193
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 59; Conference: Annual meeting of the American Nuclear Society, Atlanta, GA (USA), 4-8 Jun 1989; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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