Transient analysis of the new Cold Source at the FRM-II
Creators
- 1. Technical University of Munich, ZWE FRM-II, Garching (Germany)
- 2. Linde AG, Hoellriegelskreuth, Munich (DE)
- 3. TUEV Rheinland/Berlin-Brandenburg e.V, Cologne (DE)
Description
The new Cold Source (CNS) at the FRM-II research reactor is completely installed. This paper reports on the results of the transient analysis in the design status for this facility for producing cold neutrons for neutron experiments, the implementation of the results in the design of the mechanical components, the measurements at the cold tests and the comparison with the data of the transient analysis. The important load cases are fixed in the system description and the design data sheet of the CNS. A transient analysis was done with the computer program ESATAN, the nodal configuration was identical with the planned system of the CNS and the boundary conditions were chosen so, that conservative results can be expected. The following transients of the load cases in the piping system behind the inpile part 1) normal storage of D2 at the hydride storage vessel 2) breakdown of cooling system of the CNS and transfer of D2 to the buffer tank 3) rapid charge of D2 to the buffer tank with break of the insulation vacuum and flooding of Neon 4) reloading of the D2 from the buffer tank to the D2 hydride storage vessel were calculated. Additionally the temperature distribution for these transients in the connecting flanges of the systems to the inpile part were analysed. The temperature distributions in the flange region were take into account for the strength calculation of the flange construction. The chosen construction shows allowable values and a leak tight flange connection for the load cases. The piping system was designed to the lowest expected temperatures. The load cases in the moderator tank were take into account in the stress analysis and the fatigue analysis of the vacuum vessel and the moderator vessel. The results shows allowable stresses. The results shows that a transient analysis is necessary and helpful for good design of the CNS. (author)
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36019454.pdf
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Additional details
Publishing Information
- Imprint Title
- IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors
- Imprint Pagination
- 346 p.
- Journal Page Range
- [23 p.]
- Report number
- INIS-XA-C--030
Conference
- Title
- 9. meeting of the International Group On Research Reactors
- Acronym
- IGORR 9
- Dates
- 24-28 Mar 2003
- Place
- Sydney (Australia)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36019454
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COLD NEUTRONS; DESIGN; FLANGES; FRM-II REACTOR; LEAKS; LOSS OF COOLANT; LOSS OF FLOW; REACTOR COOLING SYSTEMS; STRESS ANALYSIS; TEMPERATURE DISTRIBUTION; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BARYONS; COOLING SYSTEMS; ELEMENTARY PARTICLES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAVY WATER MODERATED REACTORS; NEUTRONS; NUCLEONS; POOL TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs, 17 figs, 6 tabs