Experimental Validation of RELAP5 and TRACE5 for Licensing Studies of the Boron Injection System of Atucha II
Creators
- 1. Nuclear Regulatory Authority of Argentina, Buenos Aires, C1429BNP (Argentina)
- 2. School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907 (United States)
Description
This paper presents an experimental validation of RELAP5 and TRACE5 for licensing studies of the Atucha II-PHWR nuclear power plant. A scaled experimental facility, representing the boron injection system of Atucha II, was built. The system has a fundamental importance for loss of coolant accidents (LOCA) and anticipated transients without scram (ATWS). The experiment consists of the discharge of a tank that represents the boron tank filled with air or a mixture of air-water onto a discharge tank that represents the moderator tank. Both tanks are connected by a pipe which includes a valve and an orifice plate to model the pressure losses due to the fittings in the real system. The pressure and water level measured in the tanks are compared with the RELAP5 and TRACE5 predictions. The codes predict the pressure in the tanks accurately. However, both codes overpredict the heat transfer in the boron tank air-water interface which produces a greater expansion of the air which leads to a small discrepancy in the boron tank level prediction
Additional details
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations (Print)
- Journal Volume
- 2011
- Journal Issue
- 2011
- Journal Page Range
- p. 12
- ISSN
- 1687-6075
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 42050624
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCIDENTS; ATUCHA-2 REACTOR; BORON; DATA ACQUISITION SYSTEMS; ENERGY CONSERVATION; LICENSING; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PIPES; SAFETY INJECTION; VALIDATION; WATER MODERATED REACTORS
- Descriptors DEC
- ACCIDENTS; ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; NUCLEAR FACILITIES; PHWR TYPE REACTORS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SEMIMETALS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES