skip to main content

Title: Optimization of small long-life PWR based on thorium fuel

A conceptual design of small long-life Pressurized Water Reactor (PWR) using thorium fuel has been investigated in neutronic aspect. The cell-burn up calculations were performed by PIJ SRAC code using nuclear data library based on JENDL 3.2, while the multi-energy-group diffusion calculations were optimized in three-dimension X-Y-Z geometry of core by COREBN. The excess reactivity of thorium nitride with ZIRLO cladding is considered during 5 years of burnup without refueling. Optimization of 350 MWe long life PWR based on 5% {sup 233}U & 2.8% {sup 231}Pa, 6% {sup 233}U & 2.8% {sup 231}Pa and 7% {sup 233}U & 6% {sup 231}Pa give low excess reactivity.
Authors:
 [1] ;  [2] ; ; ;  [1]
  1. Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Science, Bandung Institute of Technology. Jalan Ganesha 10, Bandung (Indonesia)
  2. (Indonesia)
Publication Date:
OSTI Identifier:
22488952
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1677; Journal Issue: 1; Conference: 5. international conference on mathematics and natural sciences, Bandung (Indonesia), 2-3 Nov 2014; Other Information: (c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; BURNUP; CLADDING; COMPUTER CALCULATIONS; DESIGN; DIFFUSION; J CODES; NUCLEAR DATA COLLECTIONS; OPTIMIZATION; PROTACTINIUM 231; PWR TYPE REACTORS; REACTIVITY; REACTOR CORES; REACTOR FUELING; S CODES; THORIUM; URANIUM 233