STREAC--A BOILING WATER REACTOR THERMAL AND HYDRAULIC CODE
Technical Report
·
OSTI ID:4789790
STREAC is an IBM-704 code designed to calculate the steady-state thermal and hydraulic behavior of one-pass natural circulation boiling reactors. Given the power distribution along the axis of each box in a multichannel reactor under the assumption of axial and radial power separability, the code yields steam void distributions, inlet velocities, and pressure drops for each box. Further information is also obtained on pressure differentials and velocity behavior for the worst channel when the power is increased. In addition, input water number densities can be obtained for nuclear calculation. (auth)
- Research Organization:
- Combustion Engineering, Inc. Nuclear Div., Windsor, Conn.
- NSA Number:
- NSA-16-031251
- OSTI ID:
- 4789790
- Report Number(s):
- CEND-124; IDO-19025
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermalhydraulic calculation for boiling water reactor and its natural circulation component
Benchmarking of the FIBWR2 transient BWR (boiling water reactor) core hydraulics code
CALCULATION OF DEPARTURE FROM NUCLEATE BOILING CONDITIONS FOR THE SPERT III REACTOR IN THE HIGH PRESSURE REGION
Journal Article
·
Wed Sep 30 00:00:00 EDT 2015
· AIP Conference Proceedings
·
OSTI ID:22488954
Benchmarking of the FIBWR2 transient BWR (boiling water reactor) core hydraulics code
Conference
·
Fri Jun 01 00:00:00 EDT 1990
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6125459
CALCULATION OF DEPARTURE FROM NUCLEATE BOILING CONDITIONS FOR THE SPERT III REACTOR IN THE HIGH PRESSURE REGION
Technical Report
·
Tue Apr 17 23:00:00 EST 1962
·
OSTI ID:4785603