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Liquid Metal Coolant Disposal

#1767


Development of Components and Design Specification on the Facilities for Conversion into Safe Condition of the BR-10 Reactor Liquid Metal Coolant Radwaste and Related Section of the Reactor Decomissioning Project

Tech Area / Field

  • FIR-DEC/Decommissioning/Fission Reactors

Status
8 Project completed

Registration date
17.01.2000

Completion date
27.01.2005

Senior Project Manager
Tocheny L V

Leading Institute
FEI (IPPE), Russia, Kaluga reg., Obninsk

Supporting institutes

  • State Special Project Institute, Russia, Moscow\nObninsk Ingineering Center NIKIMT, Russia, Kaluga reg., Obninsk

Collaborators

  • CEA/DEN/DPA/Saclay, France, Gif-sur-Yvette Cedex

Project summary

Reactor decommissioning is a topical issue of nuclear power development. No experience has been gained in Russia on decommissioning of sodium cooled fast reactors.

The first approach to this problem solution will be made on the experimental BR-10 reactor that has been in operation for over 40 years (including operation with plutonium fuel for 17 years).

Prior to the start of work on this Project (proposed/desired date is May 2000), the following stages of work will be implemented with issuing related documents:

· Choosing and experimental justification of technology of conversion into safe condition of the BR-10 reactor liquid metal coolant radwaste, cold traps, etc. (on condition of support of ISTC No. 779-98 Project to be completed in April 2000).

· Project of the BR-10 reactor decommissioning, except for section related to the above technologies concerning radioactive alkali metals.

Joint studies on the issues of sodium cooled fast reactor decommissioning are included in the Agreement between RF Minatom and CEA France in the area of fast reactor development within the framework of specially established Working Group № 9. Exchange of experience gained on both sides goes on successively, as well as development of joint research programs. Results of work on the ISTC № 779 Project have been reported on the regular basis to the members of WG-9. The Group has approved this proposal as the new ISTC Project. Appropriate supporting letter was sent from CEA France to the European Commission (see attached copy). Carrying out works on the Project has international importance: the results are of great interest for France, UK, Japan, USA and Germany.

French-Russian seminars are planned to be held in turn in France and in Russia to discuss on the results of the Project implementation under this proposal.

Technical reports will be sent to Mr. J. Nokhamzon, Project Collaborator (Fax: 33169085784, Gif Sur Yvette, France).

Below are presented directions of work planned on this Project.

Direction 1 (SSC RF IPPE)

1. Summarizing results of studies on technology performed earlier and issuing design specifications on test facilities, equipment and devices for GUP OITs NIKIMT (direction 2) and GSPI (direction 3).

2. Development of equipment and issuing design documentation on the topics related to the SSC RF IPPE:


a) assuring maximum possible extent of Na-K alloy purification from mercury, cesium and tritium;
b) conversion to the safe condition of all sodium and sodium-potassium radwaste (after preliminary purification carried out on the facilities – see item a);
c) cold trap preparation for long-term storage;
d) preparation of graphite based caesium traps for long-term storage;
e) safety analysis of technology of reprocessing of alkali metal radwaste and conversion of related equipment into the safe condition.

Direction 2 (GUP OITs NIKIMT) – Developing, choosing and describing the complex of equipment and devices for carrying out works on components dismantling and room cleaning. Issue of basic designs on:


a) equipment and devices used earlier in other fields of nuclear power and adapted for the BR-10 reactor conditions;
b) Special equipment and devices for implementing the process of conversion into safe condition of the cold traps and graphite based traps of caesium;
c) Special equipment and devices for implementing the process of conversion into safe condition of alkali metal radwaste.

Direction 3 (GSPI) – Development and issuing of technical documents related to the section of the BR-10 reactor decommissioning Project on technology of radioactive alkali metal management and required equipment:

a) Design approaches on modification of existing systems of the BR-10 reactor for implementation of alkali metal purification from mercury, cesium and tritium;

b) Design approaches on implementation of process of conversion to the safe condition of alkali metal radwaste;

c) Design approaches on realization of conversion to the safe condition of cold traps and cesium traps.

Carrying out works on this Project would facilitate optimization of the whole complex of technological procedures (defined earlier in #779 Project) resulting in combined technology and issuing related documents required for manufacturing components and installing facilities for conversion to the safe condition of the BR-10 reactor radwaste.


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