New spacer grid to enhance mechanical/structural performance
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
- 2. 1174 Engineering Lab., University of Maryland, College Park, MD (United States)
- 3. Division of Mechanical and Information Management Engineering, Hanyang Univ., Ansan City (Korea, Republic of)
Description
A spacer grid (SG), which supports nuclear fuel rods (FRs) laterally and vertically with a friction grip, is one of the most important structural components in a PWR fuel. The forms of the grid straps and spring form are known to be closely related with the SG crush strength and the integrity of FR support, respectively. In this study, a new SG form and its manufacturing technology were suggested for enhancing the integrity of the FR support and the SG crush strength by using a systematic optimization technique without significantly increasing the pressure drop across the reactor core. Finite element (FE) analysis and crush strength tests on the new SG form were carried out to check the performance enhancement compared with commercial SGs. According to the results, it is estimated that the actual critical load enhancement of the SG is approximately up to 30%, and the actual contact area, when an FR is inserted into an SG cell, is more than double for the new SG form. And also, some design variables that affect the SG crush strength were classified and their effects on the crush strength were investigated by an FE analysis and a crush strength test. (author)
Availability note (English)
Available from http://dx.doi.org/10.3327/jnst.47.295Additional details
Identifiers
- DOI
- 10.3327/jnst.47.295;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 47
- Journal Issue
- 3
- Journal Page Range
- p. 295-303
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 41125687
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FINITE ELEMENT METHOD; FRETTING CORROSION; FUEL INTEGRITY; FUEL RODS; GRIDS; LASER WELDING; MECHANICAL TESTS; OPTIMIZATION; PWR TYPE REACTORS; SPACERS; SPRINGS
- Descriptors DEC
- CALCULATION METHODS; CHEMICAL REACTIONS; CORROSION; ELECTRODES; ENRICHED URANIUM REACTORS; FABRICATION; FUEL ELEMENTS; JOINING; MACHINE PARTS; MATERIALS TESTING; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WELDING
Optional Information
- Notes
- 25 refs., 18 figs., 3 tabs.