Analysis of the chemical behavior of iodine in the suppression tank of the LOFT facility during experiment LP-FP-2 with IODE and IMPAIR-2/M
Creators
- 1. Nuclear Technology Inst., Madrid (Spain). Centro de Investigaciones Energeticas Medioambientales y Tecnologicas
Description
The significance of iodine for source term quantification has been studied by investigating its chemical behavior under the prototypical conditions of a hypothetical severe accident within the containment. As a result, some computer codes were developed and their validation is currently under way. The loss-of-fluid test (LOFT) program was one of the most relevant research projects in the area of nuclear safety. Its last experiment, LP-FP-2, simulated a V-sequence. A great deal of information was recorded on the fission product release, transport, and deposition. A theoretical approach to the chemical behavior of iodine in the blowdown suppression tank (BST) of the LOFT facility was attempted with the IODE and IMPAIR-2/M codes. The comparison of the predictions with the existing experimental data led to the conclusion that the BST system behaved as a low-volatility system, with most of the iodine in the form of the soluble nonvolatile species iodide. Only a partial conversion to volatile molecular iodine was observed due to the presence of radiation. However, the intensity of the γ field was so weak that this transformation was not quantitatively meaningful
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 106
- Journal Issue
- 2
- Journal Page Range
- p. 168-176.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25067294
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT SYSTEMS; FISSION PRODUCT RELEASE; I CODES; IODINE ISOTOPES; LOFT REACTOR; LOW PRESSURE COOLANT INJECTION; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SENSITIVITY ANALYSIS; SOURCE TERMS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINMENT; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS