Published 1986
| Version v1
Report
Simulation of the preliminary General Electric SP-100 space reactor concept using the ATHENA computer code
Description
The capabilities of the ATHENA computer code for simulating the transient thermal-hydraulic behavior of a space reactor have been demonstrated. This represents the first known application of a transient thermal-hydraulic space reactor system model incorporating heat pipes. The current ATHENA heat pipe model is preliminary, excluding its use for calculating very severe transient sequences. Anticipated near term improvements in ATHENA include adding potassium as a working fluid and upgrading the heat pipe model to simulate sonic and entrainment performance limits. Longer term, upgrading ATHENA for modeling the solid-liquid-vapor working fluid phases associated with space reactor startup and shutdown events is anticipated
Additional details
Publishing Information
- Imprint Title
- Transactions of the symposia on space nuclear power systems. Summaries 1986
- Journal Page Range
- p. RS-11.1-RS-11.3.
- Report number
- CONF-860102--Summs
Conference
- Title
- 3. symposium on space nuclear power systems.
- Dates
- 13-16 Jan 1986.
- Place
- Albuquerque, NM (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18100664
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- A CODES; FLUID FLOW; HEAT PIPES; PERFORMANCE; POWER; SPACE POWER REACTORS; SPECIFICATIONS; TEMPERATURE DEPENDENCE; THEORETICAL DATA; TIME DEPENDENCE
- Descriptors DEC
- COMPUTER CODES; DATA; INFORMATION; MOBILE REACTORS; NUMERICAL DATA; POWER REACTORS; REACTORS