• Home
• About Us
  • What's New
  • Press Room
  • Contacts
  • Vacancies
  • Practical Info
  • Register
  • Web Links
  • List of Acronyms
• Work Areas
  • Nuclear Safety
  • Radioactive Waste
  • Radiological Protection
  • Nuclear Development
  • Nuclear Science
  • Nuclear Law 
  • Joint Projects
  • Sustainable Development
  • Civil Society
• Data Bank
  • Nuclear Data 
  • TDB Project 
  • Computer Programs
• Publications
  • By Subject 
  • Recently Published
  • NEA News
  • Policy Papers
• Press Room
• Search

[Program Service | Recent programs]

CSNI0002 LOFT/LP-LB-1. (Abstract last modified 20-SEP-1989)


LOFT/LP-LB-1, Loss of Fluid Test, Large-Break LOCA Experiment

---

Abstract Table of Contents:

NAME | COMPUTER | PROBLEM | SOLUTION | RESTRICTIONS | CPU | FEATURES | AUXILIARIES | STATUS | REFERENCES | REQUIREMENTS | LANGUAGE | OPERATING SYSTEM | OTHER RESTRICTIONS | AUTHOR | MATERIAL | CATEGORIES |

---

1. NAME OR DESIGNATION - LOFT/LP-LB-1.


2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name         Package-ID  Status
LOFT/LP-LB-1         CSNI0002/01 Arrived

Machines used:
Package-ID     Orig.Computer                       Test Computer
CSNI0002/01    Many Computers                      

3. DESCRIPTION OF TEST FACILITY - The LOFT Integral Test Facility is a scale model of a LPWR. The intent of the facility is to model the nuclear, Thermal-hydraulic phenomena which would take place in a LPWR during a LOCA. The general philosophy in scaling coolant volumes and flow areas in LOFT was to use the ratio of the LOFT core [50 MW(t)] to a typical LPWR core [3000 MW(t)]. For some components, this factor is not applied; however, it is used as extensively as practical. In general, components used in LOFT are similar in design to those of a LPWR. Because of scaling and component design, the LOFT LOCE is expected to closely model a LPWR LOCA.


4. DESCRIPTION OF TEST - Experiment LP-LB-1 was conducted on 3 February 1984 in the Loss-of-Fluid Test (LOFT) facility at the Idaho National Engineering Laboratory under the auspices of the Organization for Economic Cooperation and Development. The primary objectives of Experiment LP-LB-1 were to determine system transient characteristics and to assess code predictive capabilities for design basis large-break loss-of-coolant accidents in pressurized water reactors (PWRs). This experiment simulated a double-ended offset shear of one inlet pipe in a four-loop PWR and was initiated from conditions representative of licensing limits in a PWR. Other boundary conditions for the simulation were loss of offsite power, rapid primary coolant pump coastdown, and United Kingdom minimum safeguard emergency core coolant injection rates. The nuclear fuel rods were not pressurized. The transient was initiated by opening the quick-opening blowdown valves in the broken loop hot and cold legs.


5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS - Short core and steam generator, excessive core bypass, other scaling compromises, and lack of adequate measurements in certain areas.


6. PHENOMENA TESTED - Phase separation, core heat transfer, ECC bypass and penetration, and quench front propagation.


7. SPECIAL FEATURES OF EXPERIMENT - Only integral research facility with a nuclear core.


8. COUNTERPART EXPERIMENTS - Semiscale


9. STATUS
CSNI0002/01: 20-SEP-1989 Arrived at NEADB


10. REFERENCES  - 
CSNI0002/01:
- OECD LOFT Experiment LP-LB-1 Data Results
- James P. Adams and Jonathan C. Birchley:
Quick-Look Report on OECD LOFT Experiment LP-LB-1
OECD LOFT-T-3504 (February 1984)
- Charles L. Nalezny:
Summary of Nuclear Regulatory Commission's
LOFT Program Experiments
NUREG/CR-3214 - EGG-2248 (July 1983)
- Charles L. Nalezny:
Summary of Nuclear Regulatory Commission's
LOFT Program Research Findings
NUREG/CR-3005 - EGG-2231 (April 1985)
- D.L. Reeder:
LOFT System and Test Description
NUREG/CR-0247 (TREE-1208) July 1978.
- J. Fell and S.M. Modro:
An Account of the OECD LOFT Project
OECD LOFT-T-3907 May 1990.
- The OECD/LOFT Project, Achievements and Significant Results
Proceedings of an Open Forum, 9-11 May 1990, Madrid, Spain
printed in 1991
- Technical Considerations for LOFT Consortium Test Plan,
Prepared for discussion by LOFT Consortium Working Group Meeting
Munich, Germany, July 15-16, 1982 (SEN/LOFT(82)6)
- S.M. Modro, S.N. Aksan, V.T. Berta and A.B. Wahba
Review of LOFT Large Break Experiments
Topical Report OECD LOFT-T-3900 (August 1988)


11. TEST DESIGNATION - LP-LB-1


12. PROGRAMMING LANGUAGE(S) USED -
CSNI0002/01: 


15. ESTABLISHMENT 
        Idaho National Engineering Laboratory 
        EG&G Idaho 
        Idaho Falls, Idaho 83415 
        UNITED STATES


16. MATERIAL AVAILABLE -
CSNI0002/01:
Directory     (Total all files: 89.1 MB)   
Control valves                   4.9 MB    
Computed parameters              5.5 MB    
Densities                        2.2 MB    
Flows                            4.8 MB    
Frequency (pump)                 0.5 MB    
Levels                           2.0 MB    
Momentum flux                    3.8 MB    
Neutron detector                 0.7 MB    
Differential pressure            5.2 MB    
Pressures                        7.2 MB    
Power                            0.1 MB    
NIS power range                  0.1 MB    
ROD position                     0.9 MB    
Rotational speed                 0.5 MB    
Temperatures                    50.7 MB    


17. CATEGORIES  - 

- Y. Integral Experiments Data, Databases, Benchmarks


Keywords: DATA, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS

---

Home - About Us - Work Areas - Data Bank - Publications - Press Room - List of acronyms - Search