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Title: Modeling High Burnup RIA Tests with FRAPTRAN

Abstract

The transient fuel performance code FRAPTRAN 1.4 has been successfully used to model reactivity-initiated accident (RIA) tests performed on three very similar high burnup pressurized water reactor (PWR) rod segments. These segments were taken from rods irradiated for 5 cycles in the Vandellos-2 reactor, and all were clad with ZIRLO™ cladding. Each RIA test was performed under different coolant conditions. The first test, CIP0-1, was performed in the CABRI reactor under 280°C flowing sodium. The second test, VA-1, was performed in the NSRR reactor in a stagnant water capsule at room temperature and atmospheric pressure. The third test, VA-3, was performed in NSRR reactor in a stagnant water capsule at 285°C and elevated pressure. Two of these tests, VA-1 and VA-3 failed and the other test, CIP0-1, did not fail.

Authors:
 [1]
  1. BATTELLE (PACIFIC NW LAB)
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1489670
Report Number(s):
PNNL-SA-74451
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Conference
Resource Relation:
Conference: Proceedings of the LWR Fuel Performance Meeting/TopFuel/WRFPM 2010, September 26-29, 2010, Orlando, Florida
Country of Publication:
United States
Language:
English
Subject:
FRAPTRAN, reactivity initiated accident

Citation Formats

Geelhood, Kenneth J. Modeling High Burnup RIA Tests with FRAPTRAN. United States: N. p., 2010. Web.
Geelhood, Kenneth J. Modeling High Burnup RIA Tests with FRAPTRAN. United States.
Geelhood, Kenneth J. Fri . "Modeling High Burnup RIA Tests with FRAPTRAN". United States.
@article{osti_1489670,
title = {Modeling High Burnup RIA Tests with FRAPTRAN},
author = {Geelhood, Kenneth J.},
abstractNote = {The transient fuel performance code FRAPTRAN 1.4 has been successfully used to model reactivity-initiated accident (RIA) tests performed on three very similar high burnup pressurized water reactor (PWR) rod segments. These segments were taken from rods irradiated for 5 cycles in the Vandellos-2 reactor, and all were clad with ZIRLO™ cladding. Each RIA test was performed under different coolant conditions. The first test, CIP0-1, was performed in the CABRI reactor under 280°C flowing sodium. The second test, VA-1, was performed in the NSRR reactor in a stagnant water capsule at room temperature and atmospheric pressure. The third test, VA-3, was performed in NSRR reactor in a stagnant water capsule at 285°C and elevated pressure. Two of these tests, VA-1 and VA-3 failed and the other test, CIP0-1, did not fail.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2010},
month = {10}
}

Conference:
Other availability
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