Published January 1995 | Version v1
Journal article Metadata-only

Numerical investigation of fuel fragments dynamics in liquid lead coolant after accident with fast reactor core destruction

Creators

  • 1. Moskovskij Inzhenerno-Fizicheskij Inst., Moscow (Russian Federation)
  • 2. Nauchno-Issledovatel'skij i Konstruktorskij Inst. Ehnergotekhniki, Moscow (Russian Federation)

Description

Results on two-dimensional convection investigation estimates relative to the lead coolant containing solid fragments of reactor heat-releasing fuel are presented according to the task the consequences of the accident connected with fast reactor core destruction are modeled. The convective flows are determined through fuel and heat release distribution. The heat release due to neutron-physical processes by formation of fuel configurations close to critical ones is accounted for along with the residual heat release. 11 refs., 3 figs

Additional details

Additional titles

Original title (Russian)
Моделирование динмики фрагментов топлива в жидком свинце при анализе аварии с разрушением активной зоны быстрого реактора

Publishing Information

Journal Title
Atomnaya Ehnergiya
Journal Volume
78
Journal Issue
1
Journal Page Range
p. 13-21.
ISSN
0004-7163
CODEN
AENGAB

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
26077461
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALGORITHMS; COMPUTERIZED SIMULATION; CONVECTION; COOLANTS; FUEL-COOLANT INTERACTIONS; INCOMPRESSIBLE FLOW; LEAD; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; MELTDOWN; MULTIPLICATION FACTORS; NAVIER-STOKES EQUATIONS; NUMERICAL SOLUTION; VISCOUS FLOW
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; DIFFERENTIAL EQUATIONS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; METALS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR ACCIDENTS; REACTORS; SIMULATION