ASME Code Stress Evaluation of Re-engineered Primary Inlet Nozzle of APR1400 Steam Generator
Creators
- 1. KEPCO International Nuclear Graduate School, Busan (Korea, Republic of)
Description
This paper presents an evaluation of stress levels and distribution in the primary inlet nozzle under design and normal operation conditions. The evaluation is carried out as per the criteria described in ASME (American Society of Mechanical Engineers) code Section III, Subsection NB-3200 (design by analysis). The material used to manufacture APR1400 Steam Generator is carbon steel SA-508, Grade 3, Class 2 and has with a nominal composition of 3/4Ni, 1/2Mo, Cr, V. The material design limits are tensile strength 550MPa and yield strength 345 MPa. The design stress intensity for the operation temperature of 343.3.deg.C (650.deg.F) is 184 MPa. The design and operating pressure for the SG are 2500 and 2250 Psi. APR1400 design uses two wet type recirculation steam generator each with a capacity to convert 2000Mw-thermal from the core coolant to steam. Each SG has two outlet nozzles and one inlet nozzle located on its hemi-spherical lower head. The inlet nozzle has an internal diameter of 42-inch. Results for Level A also meets the ASME code criterial where the highest stresses should be less than 3Sm Based on the results, it can be concluded that the APR1400 SG primary inlet nozzle design meets the required design limits as per ASME code.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2017 Fall Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [4 p.]
Conference
- Title
- 2017 Fall Meeting of the KNS
- Dates
- 25-27 Oct 2017
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49078815
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; DESIGN; NOZZLES; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; STEAM GENERATORS; STRESSES
- Descriptors DEC
- BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 13 figs, 3 tabs