Published November 2002 | Version v1
Book

SOLPREC - a code for estimating the deposition density of activated corrosion products in the primary circuits of LMFBR: development, validation and application

  • 1. Safety Engineering Div., Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
  • 2. Health and Safety Div., Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

Full text: During the normal operation of a liquid metal fast breeder reactor, activated corrosion products are produced in stainless steel, which is the structural material of the core. The products consisting mainly of 54Mn and 60Co diffuse through the cladding into the primary sodium and get deposited along the pipelines of the reactor vessel. Since this poses a radiation hazard, an estimate of this build up is essential. Using the solution and precipitation model of Polley and Skyrme, a one-dimensional code to estimate the surface and bulk concentrations was developed for the fast breeder test reactor at Kalpakkam. This paper gives an outline of this code and the relevant results

Part of:
First national conference on nuclear reactor technology

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
First national conference on nuclear reactor technology
Imprint Pagination
421 p.
Journal Page Range
p. 313

Conference

Title
1. nuclear reactor safety
Acronym
NRT-1
Dates
25-27 Nov 2002
Place
Mumbai (India)

Optional Information