Decommissioning of research reactors.

Bulletin, Tokyo Institute of Technology

“…Report, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology…”

Quality assurance program requirements for research reactors.

Format and content for safety analysis reports for research reactors.

Thermal-hydraulic conceptual design of the multiple purpose research reactor. by Lucatero, Marco Antonio

Water chemistry management in cooling system of research reactor in JAERI. by Suparit, Nitaya

Comparison of activation cross section measurements and experimental techniques for fusion reactor technology: Summary report of the IAEA Specialists' Meeting organized by the International Atomic Energy Agency in cooperation with the Japan Atomic Energy Research Institute and held at the Tokai Research Establishment, JAERI, Japan, 15 to 17 November 1993. by Pashchenko, A.B

Coolod-N2: A computer code, for the analyses of steady-state thermal-hydraulics in research reactors. March 1994. by Kaminaga, Masanori

Fusion and fast breeder reactors. by Häfele, Wolf [y otros]

Behavior of irradiated PWR [Presssurized Water Reactor] fuel under a simulated RIA [Reactivity Initiated Accident] condition: [results of NSRR [Nuclear Safety Research Reactor] tes... by Sasajima, Hideo

JAERI CONTRIBUTION FOR THE IAEA COORDINATED RESEARCH PROGRAM PHASE III [CRP - 3] ON "OPTIMIZING OF REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAMES AND THEIR ANALYSIS". by Onizawa, Kunio

An advanced method of heterogeneous reactor theory. by Kochurov, Boris P.

COMPARISON BETWEEN A STEADY-STATE FUSION REACTOR AND AN INDUCTIVELY DRIVEN PULSE REACTOR -STUDY AS A POWER PLANT. by Horiike, Hiroshi

Sensitivity analysis of JENDL-3.2 based on benchmark calculations for fast reactors. by Zhao, Pintai

Hydrogen formation in metals and alloys during fusion reactor operation. by Zimin, Sergei

Development of integrated insulation joint for cooling pipe in tokamak reactor. by Satoshi, Nishio

Thermal durability of modified synroc material as reactor fuel matrix. by Kikuchi, Akira

Embrittlement and mechanistic interpretation of reactor pressure vessel and internal materials.

Data book of the isotopic composition of spent fuel in light water reactors. March 1994. by Naito, Yoshitaka

Design concept of control system for cryogenic distillation columns of fusion reactor. by Yamanishi, Toshihiko