Published 2007 | Version v1
Miscellaneous

Gas-Net: a two-dimensional network code for prediction of core flow and temperature distribution in the prismatic gas reactor

  • 1. Argonne National Laboratory, Argonne, Illinois (United States)

Description

In the prismatic high temperature gas reactor the coolant that bypasses fueled regions by way of leakage paths can have a significant effect on core temperatures. Large uncertainty in the bypass flow leads to increased operating and safety margins and reduced high temperature performance. The GAS-NET computer code has been developed to investigate the dependence of core temperature distribution on phenomena responsible for coolant bypass. The code is based on a two-dimensional network model for the coolant paths. It solves the one-dimensional conservation balances associated with each elemental flow path through and between fuel, fuel control, reflector control, and solid reflector elements. The code has been used to study the sensitivity of fuel channel coolant temperatures to uncertainties associated with core pressure loss data, leakage past core support seals, leakage from between stacked elements, and leakage past control rods in control rod holes. Ultimately such results can be used to prioritize experiments aimed at reducing uncertainties to achieve reduced operating and safety margins. (author)

Availability note (English)

Available from: SFEN, 5 rue des Morillons, 75015 Paris (France)

Additional details

Publishing Information

Imprint Pagination
10 p.
Report number
INIS-FR--08-0985

Conference

Title
ICAPP 2007 - International congress on advances in nuclear power plants. The nuclear renaissance at work
Dates
13-18 May 2007
Place
Nice Acropolis (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
39090706
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; G CODES; GAS FLOW; HTGR TYPE REACTORS; LEAKS; PARAMETRIC ANALYSIS; REACTOR CORES
Descriptors DEC
COMPUTER CODES; FLUID FLOW; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION

Optional Information

Notes
11 refs.