Published June 1, 2018 | Version v1
Report

RELAP5-3D Pre-test Prediction for High Temperature Test Facility Test PG-26

  • 1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

Description

The RELAP5-3D computer code has been used to perform a pre-test prediction for Test PG-26 in the High Temperature Test Facility at Oregon State University. Test PG-26 will simulate a pressurized conduction cooldown transient following a trip of the primary coolant system gas circulator. The facility is initialized with a steady-state power of 700 kW and prototypic core inlet and outlet helium coolant temperatures of 259 and 687°C, respectively. Sensitivity calculations addressed the flow coastdown time, the reactor cavity cooling system flow rate and temperature, and decay power.

Availability note (English)

Available from https://inldigitallibrary.inl.gov/sites/sti/sti/Sort_5690.pdf; PURL: http://www.osti.gov/servlets/purl/1467561/

Additional details

Publishing Information

Imprint Pagination
66 p.
Report number
INL/EXT--18-45717-Rev000

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
50053786
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COMPUTER CODES; PRIMARY COOLANT CIRCUITS; TEMPERATURE RANGE 0400-1000 K; TEST FACILITIES
Descriptors DEC
COOLING SYSTEMS; ENERGY SYSTEMS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; TEMPERATURE RANGE

Optional Information

Contract/Grant/Project number
AC07-05ID14517
Funding organization
USDOE Office of Nuclear Energy - NE (United States)
Secondary number(s)
OSTIID--1467561