Computation of concentration changes of heavy metals in the fuel assemblies with 1.6% enrichment by ORIGEN code for VVER-1000

• Autorzy: Rahgoshay M.
• Języki publikacji: EN

Abstrakty

EN

ORIGEN code is a widely used computer code for calculating the buildup, decay, and processing of radioactive materials. During the past few years, a sustained effort was undertaken by ORNL to update the original ORIGEN code [4] and its associated data bases. The results of this effort were updated on the reactor model, cross section, fission product yields, decay data, decay photon data and the ORIGEN computer code itself. In this paper we have obtained concentration changes of uranium and plutonium isotopes by ORIGEN code at different burn-up and then the results have been compared with VVER-1000 results in the first fuel cycle for fuel assemblies with 1.6% enrichment in the BUSHEHR Nuclear Power Plant.

Słowa kluczowe

EN

ORIGEN code; burn-up; heavy metals; BUSHEHR Nuclear Power Plant

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2006
• Tom: Vol. 51, nr 3
• Strony: 161--167
• Opis fizyczny: Bibliogr. 4 poz., rys.

Twórcy

autor

Rahgoshay M.

• Department of Nuclear Engineering, Faculty of Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran, Tel.: [phone], Fax: [phone],

Bibliografia

• 1. BUSHEHR Nuclear Power Plant (2003) Final Safety Analysis Report (FSAR). Chapter 4
• 2. Idaho National Engineering Laboratory (1995) RELAP/MODE3.2.2 Beta. INEL Lockheed Idaho Technologies Company, Idaho Falls
• 3. ORNL (1971) Nuclear Reactor Core Analysis Code:CITATION. ORNL-TM-2496, Rev. 2, Contract No.W-7405-eng-26
• 4. ORNL (1980) A user’s manual for the ORIGEN computer code. ORNL/TM-7175, Contract No. W-7405-eng-26