Статья

Thermal-hydraulic analysis of a research reactor on personal computer with TARR code

Ngo Huy CanNguyen Manh LanInstitute of Mechanics NCSR of V£etnam SU1vlli1ARYTran Van TranInstitute of Mechanics NCSR of V£etnam SU1vlli1ARY

Vietnam Journal of Mechanicsjournal1992en

ABI

Аннотация

The code has been created for thermal-hydraulic calculation of stationary regime of nuclear research reactor, using personal computer. The main objective of the code is to compute the thermal parameters in the reactor core in order to avoid any accident. The code can be applied for many fuel assemblies available in research reactors.

Темы

Nuclear reactor physics and engineering Nuclear Engineering Thermal-Hydraulics Graphite, nuclear technology, radiation studies

Идентификаторы

DOI: 10.15625/0866-7136/10233

Цитирования и источники

Цитирований: 0Использованных источников: 2

Показатели — AkademScholar · Скоро