Source term calculations - Ringhals 2 PWR
- 1. Studsvik Eco and Safety AB, Nykoeping (Sweden)
Description
This project was performed within the fifth and final phase of sub-project RAK-2.1 of the Nordic Co-operative Reactor Safety Program, NKS.RAK-2.1 has also included studies of reflooding of degraded core, recriticality and late phase melt progression. Earlier source term calculations for Swedish nuclear power plants are based on the integral code MAAP. A need was recognised to compare these calculations with calculations done with mechanistic codes. In the present work SCDAP/RELAP5 and CONTAIN were used. Only limited results could be obtained within the frame of RAK-2.1, since many problems were encountered using the SCDAP/RELAP5 code. The main obstacle was the extremely long execution times of the MOD3.1 version, but also some dubious fission product calculations. However, some interesting results were obtained for the studied sequence, a total loss of AC power. The report describes the modelling approach for SCDAP/RELAP5 and CONTAIN, and discusses results for the transient including the event of a surge line creep rupture. The study will probably be completed later, providing that an improved SCDAP/RELAP5 code version becomes available. (au) becomes available. (au)
Availability note (English)
Available from INIS in electronic formFiles
29042634.pdf
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Additional details
Publishing Information
- ISBN
- 87-7893-036-7
- Imprint Pagination
- 30 p.
- Report number
- NKS-RAK--2(97)TR-A6
INIS
- Country of Publication
- Denmark
- Country of Input or Organization
- Denmark
- INIS RN
- 29042634
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; DESIGN BASIS ACCIDENTS; FISSION PRODUCT RELEASE; M CODES; MELTDOWN; RINGHALS-2 REACTOR; SAFETY ANALYSIS; SOURCE TERMS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract NKS/RAK-2.1