Monteburns and HELIOS calculated spent fuel isotopics compared to measured values

Journal Article · Wed Sep 01 04:00:00 EDT 1999 · Transactions of the American Nuclear Society

OSTI ID:678164

Charlton, W S; Perry, R T ^[1]; Parish, T A ^[2]

---

1. Los Alamos National Lab., NM (United States)
2. Texas A and M Univ., College Station, TX (United States)

Accurate spent-fuel isotopics are crucial for use in fuel management, mixed oxide fuel depletion calculations, reprocessing analyses, safeguards systems, and waste disposal studies. Two recently developed reactor analysis codes for calculating spent-fuel isotopics are the HELIOS code system, produced and maintained by Studsvik ScandPower, and the Monteburns code, created at Los Alamos National Laboratory. Both of these codes can be used to evaluate reactors with complex geometries and material compositions. To test the accuracy of HELIOS and Monteburns for the calculation of spent-fuel isotopics, both codes were benchmarked to measurements selected from the literature.

• OSTI ID: 678164
• Report Number(s): CONF-990605--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 80; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS
BENCHMARKS
BURNUP
COMPARATIVE EVALUATIONS
H CODES
ISOTOPE RATIO
M CODES
PWR TYPE REACTORS
SPENT FUELS
USES