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
Identifiers
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