NEUTRONIC ANALYSIS OF A HEAT-PIPE COOLED REACTOR.
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- Acta Polytechnica CTU Proceedings, 2023, v. 44, p. 19, doi. 10.14311/APP.2023.44.0019
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- Article
Works matching IS 23365382 AND DT 2023 AND VI 44
Results: 5
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2
SIMULATION OF THE COMPRESSION TEST OF THE ZR1NB FUEL CLADDING RING.
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- Acta Polytechnica CTU Proceedings, 2023, v. 44, p. 28, doi. 10.14311/APP.2023.44.0028
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- Publication type:
- Article
3
EVALUATION OF ATLHAMC12 SUBCHANNEL CODE FOR TOTAL LOSS OF FLOW SCENARIO.
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- Acta Polytechnica CTU Proceedings, 2023, v. 44, p. 13, doi. 10.14311/APP.2023.44.0013
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- Article
4
EFFECT OF HEAT-TREATMENT ON MATERIAL PROPERTIES OF L-DED PRINTED AUSTENISTIC ALLOY 08CH18N10T FOR NUCLEAR REACTOR APPLICATIONS.
- Published in:
- Acta Polytechnica CTU Proceedings, 2023, v. 44, p. 1, doi. 10.14311/APP.2023.44.0001
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- Publication type:
- Article
5
THERMOMECHANICAL CALCULATION WITHIN THE HERA PROGRAMME.
- Published in:
- Acta Polytechnica CTU Proceedings, 2023, v. 44, p. 5, doi. 10.14311/APP.2023.44.0005
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- Publication type:
- Article