Packaging, Transport, Storage and Security of Radioactive Material

Announcements
pp. 162-162(1)

Denial of shipments — no longer 'myth' but 'reality'
pp. 163-168(6)
Authors: Charette, M.A.; McInnes, D.

Japanese perspectives and research on packaging, transport and storage of spent fuel
pp. 169-178(10)
Authors: Saegusa, T.; Ito, C.; Yamakawa, H.; Shirai, K.

Lessons learned from the West Valley spent nuclear fuel shipment within the United States
pp. 179-188(10)
Authors: Tyacke, M.J.; Anderson, T.

Assessment of integrity of a dual-purpose metal cask after long-term interim storage: seal performance under transport conditions
pp. 189-198(10)
Authors: Yokoyama, T.; Kawakami, H.; Uchiyama, N.; Yasuda, M.; Matsuoka, S.

Operational experience of on-site transport of spent nuclear fuel in Korea
pp. 199-204(6)
Authors: Chung, S.H.; Baeg, C.Y.; Choi, B.I.; Lee, H.Y.; Kim, Y.J.

Expansion of the capabilities of the GA-4 legal weight truck spent fuel shipping cask
pp. 205-210(6)
Authors: Zimmer, A.; Razvi, J.; Johnson, L.; Welch, B.; Lancaster, D.

A methodology for the evaluation of fuel rod failures under accident conditions
pp. 211-218(8)
Authors: Rashid, J.Y.R.; Machiels, A.J.

Validation of the thermal calculation method and the applicability of confinement monitoring with a full-scale mock-up test of a concrete cask
pp. 219-228(10)
Authors: Tsuji, H.; Ito, D.; Fujinami, K.; Yamamoto, K.; Suyama, T.

Performance of the improved version of the Monte Carlo A³MCNP code in the design of cask shielding
pp. 229-236(8)
Authors: Miyake, Y.; Ohmura, M.; Hasegawa, T.; Ueki, K.; Sato, O.; Haghighat, A.; Sjoden, G.E.

Future Features
pp. 237-238(2)

Instructions to authors
pp. 239-240(2)