| TECHNICAL NOTE |
|
| Year : 2016 | Volume
: 39
| Issue : 3 | Page : 165-169 |
|
|
Health physics operating experience in transporting cleanup spent resin and verification of methodology for estimating the shielding thickness of cask
Bahadur Singh K Rautela1, Sarat R Sahu1, PS Raveendran1, Prakash K Kothare1, Sudip Ranjan Mitra1, B. S. V. Ramana Murthy2
1 Department of Atomic Energy, Health Physics Section, Tarapur Atomic Power Station 1 and 2, Tarapur Maharashtra Site, Nuclear Power Corporation of Ltd, Mumbai, Maharashtra, India
2 Department of Atomic Energy, Health Physics Section, Health Safety and Environment Group, Nuclear Power Corporation of Ltd, Mumbai, Maharashtra, India
Correspondence Address:
Bahadur Singh K Rautela
Health Physics Section, Tarapur Atomic Power Station 1 and 2, Tarapur Maharashtra Site, NPCIL, Palghar - 401 504, Maharashtra
India
 Source of Support: None, Conflict of Interest: None  | Check |
DOI: 10.4103/0972-0464.194963
|
|
|
Cleanup (CU) demineralizer of TAPS 1 and 2, containing mixed bed resins, is used to maintain reactor water chemistry. Once the bed is saturated, spent resin needs to be transferred to resin fixation facility for fixation and subsequent disposal in near-surface disposal facility. This is done by transporting the spent resin in a shielded resin transportation cask (SRTC) from radwaste building. The SRTC was manufactured with shielding thickness, based on methodology proposed by Rautela et al., “Shielding adequacy of proposed cask for transporting TAPS 1 and 2 CU spent resins.” Extensive radiation monitoring was carried out during the entire transfer and transportation process. Observed radiation levels on cask surface were within the accepted and calculated radiation levels. This paper describes verification methodology proposed by Rautela et al. and health physics operating experience during first CU spent resin transfer process at TAPS 1 and 2. |
|
|
|
| [FULL TEXT] [PDF]* |
|
 |
|
Search Pubmed for