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Title: The radiation characteristics of the transport packages with vitrified high-level waste

The calculation method of neutron yield in the (α, n) reaction for a homogeneous material of arbitrary composition is represented. It is shown that the use of the ORIGEN 2 code excluding the real elemental composition of vitrified high-level waste leads to significant underestimation of the neutron yield in the (α, n) reaction. For vitrified high-level waste and spent nuclear fuel from VVER, the neutron fluxes are analyzed. The thickness of the protective materials for a transfer cask and a shipping cask with vitrified highlevel waste are estimated.
Authors:
 [1] ; ;  [2]
  1. JSC VNIPIpromtechnologii (Russian Federation)
  2. Russian Academy of Sciences, Nuclear Safety Institute (Russian Federation)
Publication Date:
OSTI Identifier:
22471952
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Atomic Nuclei; Journal Volume: 78; Journal Issue: 11; Other Information: Copyright (c) 2015 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ALPHA REACTIONS; CALCULATION METHODS; CASKS; HIGH-LEVEL RADIOACTIVE WASTES; NEUTRON FLUX; NEUTRONS; NUCLEAR REACTION YIELD; O CODES; SPENT FUELS; VITRIFICATION; WWER TYPE REACTORS