Validation of the nuclear design code system for the HTTR using the criticality assembly VHTRC

Nozomu Fujimoto, Naoki Nojiri, Kiyonobu Yamashita

Research output: Contribution to journalArticlepeer-review

3 Citations (Scopus)

Abstract

The high temperature engineering test reactor is the first block-type HTGR designed for a 950 °C outlet gas temperature which uses low-enriched uranium fuel with burnable poison rod. For validation of the nuclear design code system for the HTTR, a critical assembly of VHTRC had been constructed. The calculation uncertainties of effective multiplication factor, neutron flux distribution, burnable poison reactivity worth, and control rod worth, temperature coefficients were evaluated. Calculation accuracy of a Monte Carlo code is also evaluated.

Original languageEnglish
Pages (from-to)155-162
Number of pages8
JournalNuclear Engineering and Design
Volume233
Issue number1-3
DOIs
Publication statusPublished - Oct 1 2004
Externally publishedYes

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering
  • Safety, Risk, Reliability and Quality

Fingerprint Dive into the research topics of 'Validation of the nuclear design code system for the HTTR using the criticality assembly VHTRC'. Together they form a unique fingerprint.

Cite this