• 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]

CSNI0074 LOBI/BT-00. (Abstract last modified 12-OCT-1988)


LOBI/BT-00, Simulation of a Loss of Feedwater Transient (LOFW)

---

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 - LOBI/BT-00.


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
LOBI/BT-00           CSNI0074/01 Report

Machines used:
Package-ID     Orig.Computer                       Test Computer
CSNI0074/01                                        

3. DESCRIPTION OF TEST FACILITY - LOBI-MOD2 is a non-nuclear two loop, high pressure integral system test facility for PWR safety research. It simulates the cooling system of a four-loop 1300 MWe PWR. It is especially designed for large and small break loss-of-coolant experiments and for special transient accident investigations. Emphasis is placed on the influence of loop components and of emergency cooling systems on the course of a reactor accident transient.


4. DESCRIPTION OF TEST - LOBI tests provide experimental data for checking and improving computer codes. In addition, they demonstrate the performance of reactor safety systems and procedures.
  
MOD2 is an extension of MOD1 25 large break loss-of-coolant experiments by the addition of components as needed for small break tests, e.g. scaled steam generators, a high pressure injection system (HPIS), secondary auxiliary feedwater injection (AFW), additional instrumentation and complete thermal insulation.
  
Test BT-00 belongs to the LOBI special transient test program and is part of the B-test series. Within the LOBI special transient test matrix this test is also called "ST-2" (scoping test no.2). Test BT-00 simulates a loss of main feedwater (LOFW) followed by a steam generator dryout and a subsequent cooldown via primary bleed and feed.
  
Scaling: The power input, the primary circuit coolant mass flow and volume are scaled down from the reactor values by a factor of 712. All the other most relevant quantities such as operating temperature, pressure, lengths and pressure drops along heat transfer surfaces have been scaled 1:1. Also the absolute heights and relative elevations of the individual system components have been kept at reactor values thus preserving the gravitational heads.


5. EXPERIMENTAL LIMITATIONS OF SHORTCOMINGS -


6. PHENOMENA TESTED - Test BT-00 consists of three consecutive phases:
- Phase 1 simulates a loss of main feedwater transient (LOFW) causing a boildown of the secondary water inventory in the steam generators followed by power scram.
- In phase 2 also auxiliary feedwater supply is interrupted to cause dryout on the secondary side and thus a primary side heat-up.
- In the final phase 3 the system is cooled down by primary side bleed and feed.
The test investigates the possibility of reproducing LOFW transients with the LOBI facility in a similar way as they would be expected for the reference plant.
  
Particular phenomena of main interest from this test are the heat-up after loss of main feed, cooldown after scram, heat-up after loss of secondary inventory and the final cooldown. During both heat-ups, pressurizer relief valve (PORV) opening is observed. The final cooldown by primary bleed and feed is performed with an open pressurizer relief valve and cold leg high pressure injection (HPIS) at an injection rate representative of two injection pumps. The behavior of the LOBI steam generators at low secondary inventories was also studied at the previous tests A1-76 and A2-90.


8. COUNTERPART EXPERIMENTS -


9. STATUS
CSNI0074/01: 12-OCT-1988 Report Only


10. REFERENCES  - 
CSNI0074/01:
- W. Kolar and W. Brewka:
LOBI Experimental Data Tape - Format Description -
Technical Note No.I.06.C1.85.49 (May 1985)
- LOBI Project - RELAP5 Base Input Data for LOBI-MOD2
LPC 85-18 (February 1985)
- J. Sanders and E. Ohlmer:
Experimental Data Report on LOBI-MOD2 Test BT-00 (LOFW)
(ISPRA LEC 86-38, Communication No. 4038)  April 1986


11. TEST DESIGNATION - BT-00.


12. PROGRAMMING LANGUAGE -CSNI0074/01: 


15. ESTABLISHMENT -
        Commission of the European Communities
        Joint Research Centre
        Ispra Establishment
        I-21020 Ispra
        ITALY


16. MATERIAL AVAILABLE -CSNI0074/01:


17. CATEGORIES  - 

- Y. Integral Experiments Data, Databases, Benchmarks


Keywords: BLOWDOWN, DATA, LOSS-OF-COOLANT ACCIDENT, PRESSURIZED WATER REACTOR, SAFETY, TRANSIENTS

---

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