Published April 2006 | Version v1
Journal article Metadata-only

SERPENT code verification during calculation of the heat transfer in uniformly heated pipes

Creators

  • 1. Rossijskij Nauchnyj Tsentr Kurchatovskij Inst. - Inst. Yadernykh Reaktorov, Moscow (Russian Federation)

Description

Paper deals with the results of the efforts to calculate the parameters of heat transfer conditions in the uniformly heated pipes on the basis of the Grnv95 and the FEI91 skeleton tables. Calculation of heat transfer is of interest when analyzing upset modes of nuclear power plants and in uniflow steam generators

Abstract (Russian)

Приводятся результаты расчета параметров режимов кризиса теплоотдачи в равномерно обогреваемых трубах, полученные с помощью скелетных таблиц Grnv95 и ФЭИ91. Расчет теплоотдачи в закризисной области также представляет значительный интерес при анализе аварийных режимов ядерных энергетических установок и в прямоточных парогенераторах

Additional details

Additional titles

Original title (Russian)
Некоторые результаты верификации кода SERPENT при расчете кризиса теплоотдачи в равномерно обогреваемых трубах

Publishing Information

Journal Title
Teploehnergetika
Journal Issue
no.4
Journal Page Range
p. 39-45
ISSN
0040-3636
CODEN
TPLOA5

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
38056078
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ALGORITHMS; CERTIFICATION; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CRITICAL HEAT FLUX; FLOW RATE; FLUX DENSITY; HEAT TRANSFER; NUCLEAR POWER PLANTS; PARAMETRIC ANALYSIS; PIPES; REACTOR ACCIDENTS; REACTOR SAFETY; S CODES; STEAM GENERATORS
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; ENERGY TRANSFER; EVALUATION; HEAT FLUX; MATHEMATICAL LOGIC; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; SIMULATION; THERMAL POWER PLANTS; TUBES; VAPOR GENERATORS

Optional Information

Notes
20 refs., 7 figs., 4 tabs.