Actions for TRAC-PF1
TRAC-PF1/MOD1 pretest predictions of MIST experiments [electronic resource].
- Published
- Los Alamos, N.M. : Los Alamos National Laboratory, 1986.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 20 : digital, PDF file
- Additional Creators
- Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Los Alamos National Laboratory is a participant in the Integral System Test (IST) program initiated in June 1983 to provide integral system test data on specific issues and phenomena relevant to post small-break loss-of-coolant accidents (SBLOCAs) in Babcock and Wilcox plant designs. The Multi-Loop Integral System Test (MIST) facility is the largest single component in the IST program. During Fiscal Year 1986, Los Alamos performed five MIST pretest analyses. The five experiments were chosen on the basis of their potential either to approach the facility limits or to challenge the predictive capability of the TRAC-PF1/MOD1 code. Three SBLOCA tests were examined which included nominal test conditions, throttled auxiliary feedwater and asymmetric steam-generator cooldown, and reduced high-pressure-injection (HPI) capacity, respectively. Also analyzed were two ''feed-and-bleed'' cooling tests with reduced HPI and delayed HPI initiation. Results of the tests showed that the MIST facility limits would not be approached in the five tests considered. Early comparisons with preliminary test data indicate that the TRAC-PF1/MOD1 code is correctly calculating the dominant phenomena occurring in the MIST facility during the tests. Posttest analyses are planned to provide a quantitative assessment of the code's ability to predict MIST transients.
- Report Numbers
- E 1.99:la-ur-86-3695
E 1.99: conf-8610135-32
conf-8610135-32
la-ur-86-3695 - Subject(s)
- Other Subject(s)
- Loss Of Coolant
- Heat Transfer
- Hydraulics
- T Codes
- Pwr Type Reactors
- Auxiliary Water Systems
- Reactor Safety Experiments
- Steam Generators
- Test Facilities
- Transients
- Accidents
- Auxiliary Systems
- Boilers
- Computer Codes
- Energy Transfer
- Fluid Mechanics
- Mechanics
- Reactor Accidents
- Reactors
- Vapor Generators
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
01/01/1986.
"la-ur-86-3695"
" conf-8610135-32"
"DE87001988"
14. water reactor safety information meeting, Gaithersburg, MD, USA, 27 Oct 1986.
Steiner, J.L.; Boyack, B.E.; Siebe, D.A. - Funding Information
- W-7405-ENG-36
View MARC record | catkey: 14368784